Journal publications of the STARS Program

Our scientists, post docs and students regularly publish articles in scientific magazines primarily in the nuclear engineering and technical field. For this purpose, each submitted article is first thoroughly reviewed and then approved.

Here you will find a selection of journals that regularly publish articles from our laboratory:

2022

Alhassan E, Rochman D, Vasiliev A, Hursin M, Koning AJ, Ferroukhi H
Iterative Bayesian Monte Carlo for nuclear data evaluation
Nuclear Science and Techniques. 2022; 33(4): 50 (31 pp.). https://doi.org/10.1007/s41365-022-01034-w
DORA PSI
Avrigeanu M, Rochman D, Koning AJ, Fischer U, Leichtle D, Costache C, et al.
Advanced breakup-nucleon enhancement of deuteron-induced reaction cross sections
European Physical Journal A: Hadrons and Nuclei. 2022; 58: 3 (13 pp.). https://doi.org/10.1140/epja/s10050-021-00659-6
DORA PSI
Cozzo C, Khvostov G, Clifford I, Ferroukhi H
Appraisal of the NRC H-uptake calculation for Swiss boiling water reactors
Nuclear Engineering and Design. 2022; 391: 111731 (5 pp.). https://doi.org/10.1016/j.nucengdes.2022.111731
DORA PSI
Dokhane A, Vasiliev A, Hursin M, Rochman D, Ferroukhi H
A critical study on best methodology to perform UQ for RIA transients and application to SPERT-III experiments
Nuclear Engineering and Technology. 2022; 54(5): 1804-1812. https://doi.org/10.1016/j.net.2021.10.042
DORA PSI
Fiorina C, Clifford I, Kelm S, Lorenzi S
On the development of multi-physics tools for nuclear reactor analysis based on OpenFOAM®: state of the art, lessons learned and perspectives
Nuclear Engineering and Design. 2022; 387: 111604 (15 pp.). https://doi.org/10.1016/j.nucengdes.2021.111604
DORA PSI
Fogliatto EO, Clausse A, Teruel FE
Development of a double-MRT pseudopotential model for tridimensional boiling simulation
International Journal of Thermal Sciences. 2022; 179: 107637 (13 pp.). https://doi.org/10.1016/j.ijthermalsci.2022.107637
DORA PSI
Jansson P, Bengtsson M, Bäckström U, Álvarez-Velarde F, Čalič D, Caruso S, et al.
Blind benchmark exercise for spent nuclear fuel decay heat
Nuclear Science and Engineering. 2022. https://doi.org/10.1080/00295639.2022.2053489
DORA PSI
Khvostov G
Modelling effects of transient FGR in LWR fuel rods during a LOCA
Journal of Nuclear Materials. 2022; 559: 153446 (26 pp.). https://doi.org/10.1016/j.jnucmat.2021.153446
DORA PSI
Maestre J, Bahamonde C, Lamas Garcia I, Kershaw K, Biancacci N, Busom J, et al.
High intensity proton beam impact at 440 GeV/c on Mo and Cu coated CfC/graphite and SiC/SiC absorbers for beam intercepting devices
Journal of Instrumentation. 2022; 17: P01019 (32 pp.). https://doi.org/10.1088/1748-0221/17/01/P01019
DORA PSI
Mager T, Fiorina C, Hursin M, Pautz A
Investigation and validation of unstructured mesh methodologies for modeling experimental reactors
Energies. 2022; 15(4): 1512 (11 pp.). https://doi.org/10.3390/en15041512
DORA PSI
Martinez-Quiroga V, Szogradi M, Schollenberger S, Sanchez-Perea M, Sandberg N, Zhongyun J, et al.
OECD/NEA PKL-4 benchmark activity. Code assessment of the relevant phenomena associated to a blind IBLOCA experiment
Nuclear Engineering and Design. 2022; 389: 111632 (20 pp.). https://doi.org/10.1016/j.nucengdes.2021.111632
DORA PSI
Moreno-Soto J, Valenta S, Berthoumieux E, Chebboubi A, Diakaki M, Dridi W, et al.
Constraints on the dipole photon strength for the odd uranium isotopes
Physical Review C: Nuclear Physics. 2022; 105(2): 024618 (14 pp.). https://doi.org/10.1103/PhysRevC.105.024618
DORA PSI
Nikitin K, Clifford I, Dokhane A, Ferroukhi H
Methodology for CPR estimations of BWR cycle specific transient reload analyses using CTF sub-channel code
Nuclear Engineering and Design. 2022; 389: 111649 (14 pp.). https://doi.org/10.1016/j.nucengdes.2022.111649
DORA PSI
Perret G, Wicaksono D, Clifford ID, Ferroukhi H
Global sensitivity analysis and bayesian calibration on a series of reflood experiments with varying boundary conditions
Nuclear Technology. 2022; 208(4): 711-722. https://doi.org/10.1080/00295450.2021.1936879
DORA PSI
Rochman D, Vasiliev A, Ferroukhi H, Koning A, Sublet J-C
Impact of H in H₂O thermal scattering data on criticality calculation: uncertainty and adjustment
EPJ Nuclear Sciences and Technologies. 2022; 8: 3 (7 pp.). https://doi.org/10.1051/epjn/2021028
DORA PSI
Scolaro A, Fiorina C, Clifford I, Pautz A
Development of a semi-implicit contact methodology for finite volume stress solvers
International Journal for Numerical Methods in Engineering. 2022; 123(2): 309-338. https://doi.org/10.1002/nme.6857
DORA PSI
Shama A, Rochman D, Caruso S, Pautz A
Validation of spent nuclear fuel decay heat calculations using Polaris, ORIGEN and CASMO5
Annals of Nuclear Energy. 2022; 165: 108758 (14 pp.). https://doi.org/10.1016/j.anucene.2021.108758
DORA PSI
Yum S, Hursin M, Vasiliev A, Vinai P, Mylonakis AG, Demazière C, et al.
Uncertainty analyses of neutron noise simulations in a Zero-Power reactor
Annals of Nuclear Energy. 2022; 174: 109157 (13 pp.). https://doi.org/10.1016/j.anucene.2022.109157
DORA PSI

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2021

Amaducci S, Colonna N, Cosentino L, Cristallo S, Finocchiaro P, Krtička M, et al.
First results of the ¹⁴⁰Ce(n,ү)¹⁴¹Ce cross-section measurement at n_TOF
Universe. 2021; 7(6): 200 (11 pp.). https://doi.org/10.3390/UNIVERSE7060200
DORA PSI
Babiano-Suárez V, Lerendegui-Marco J, Balibrea-Correa J, Caballero L, Calvo D, Ladarescu I, et al.
Imaging neutron capture cross sections: i-TED proof-of-concept and future prospects based on Machine-Learning techniques
European Physical Journal A: Hadrons and Nuclei. 2021; 57(6): 197 (17 pp.). https://doi.org/10.1140/epja/s10050-021-00507-7
DORA PSI
Clifford I, Ferroukhi H
Assessing the effects of switching from multi-channel to three-dimensional nodalisations of the core in TRACE
Nuclear Engineering and Design. 2021; 383: 111446 (15 pp.). https://doi.org/10.1016/j.nucengdes.2021.111446
DORA PSI
Dokhane A, Hursin M, Vasiliev A, Rochman D, Ferroukhi H
Recent developments in PSI BEPU analysis for SPERT-III RIA transient: ND uncertainty breakdown and kinetic parameters uncertainty assessment
Nuclear Engineering and Design. 2021; 382: 111378 (14 pp.). https://doi.org/10.1016/j.nucengdes.2021.111378
DORA PSI
Frankl M, Hursin M, Rochman D, Vasiliev A, Ferroukhi H
Nuclear data uncertainty quantification in criticality safety evaluations for spent nuclear fuel geological disposal
Applied Sciences. 2021; 11(14): 6499 (19 pp.). https://doi.org/10.3390/app11146499
DORA PSI
Khvostov G, Gorzel A
FALCON code-based analysis of PWR fuel rod behaviour during RIA transients versus new U.S.NRC and current Swiss failure limits
Nuclear Engineering and Technology. 2021; 53(11): 3741-3758. https://doi.org/10.1016/j.net.2021.06.001
DORA PSI
Konarski P, Cozzo C, Khvostov G, Ferroukhi H
Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling
Journal of Nuclear Materials. 2021; 555: 153138 (26 pp.). https://doi.org/10.1016/j.jnucmat.2021.153138
DORA PSI
Pelloni S, Rochman D
Addressing challenges in nuclear data adjustment techniques using integral experiments based upon uranium solution thermal systems
Annals of Nuclear Energy. 2021; 163: 108590 (12 pp.). https://doi.org/10.1016/j.anucene.2021.108590
DORA PSI
Pázsit I, Torres LA, Hursin M, Nylén H, Dykin V, Montalvo C
Development of a new method to determine the axial void velocity profile in BWRs from measurements of the in-core neutron noise
Progress in Nuclear Energy. 2021; 138: 103805 (11 pp.). https://doi.org/10.1016/j.pnucene.2021.103805
DORA PSI
Pérot B, Carasco C, Eléon C, Bernard S, Sardet A, El Kanawati W, et al.
Sea container inspection with tagged neutrons
EPJ Nuclear Sciences and Technologies. 2021; 7: 6 (37 pp.). https://doi.org/10.1051/epjn/2021004
DORA PSI
Rochman D, Vasiliev A, Ferroukhi H, Hursin M
Analysis for the ARIANE BM1 and BM3 samples: nuclide inventory and decay heat
EPJ Nuclear Sciences and Technologies. 2021; 7: 18 (24 pp.). https://doi.org/10.1051/epjn/2021017
DORA PSI
Rochman D, Vasiliev A, Ferroukhi H, Hursin M
Analysis for the ARIANE GU1 sample: nuclide inventory and decay heat
Annals of Nuclear Energy. 2021; 160: 108359 (19 pp.). https://doi.org/10.1016/j.anucene.2021.108359
DORA PSI
Rochman D, Vasiliev A, Ferroukhi H, Hursin M, Ichou R, Taforeau J, et al.
Analysis for the ARIANE GU3 sample: nuclide inventory and decay heat
EPJ Nuclear Sciences and Technologies. 2021; 7: 14 (24 pp.). https://doi.org/10.1051/epjn/2021013
DORA PSI
Rochman DA, Bauge E
Fission yields and cross sections: correlated or not?
EPJ Nuclear Sciences and Technologies. 2021; 7: 5 (9 pp.). https://doi.org/10.1051/epjn/2021005
DORA PSI
Rochman D, Hursin M, Vasiliev A, Ferroukhi H
Impact of H in H₂O thermal scattering data on depletion calculation: k_∞, nuclide inventory and decay heat
EPJ Nuclear Sciences and Technologies. 2021; 7: 24 (8 pp.). https://doi.org/10.1051/epjn/2021027
DORA PSI
Rochman D, Shama A, Pudollek S, Caruso S, Pautz A
Uncertainty analyses of spent nuclear fuel decay heat calculations using SCALE modules
Nuclear Engineering and Technology. 2021; 53(9): 2816-2829. https://doi.org/10.1016/j.net.2021.03.013
DORA PSI
Schnabel G, Sjöstrand H, Hansson J, Rochman D, Koning A, Capote R
Conception and software implementation of a nuclear data evaluation pipeline
Nuclear Data Sheets. 2021; 173: 239-284. https://doi.org/10.1016/j.nds.2021.04.007
DORA PSI
Scolaro A, Van Uffelen P, Fiorina C, Schubert A, Clifford I, Pautz A
Investigation on the effect of eccentricity for fuel disc irradiation tests
Nuclear Engineering and Technology. 2021; 53(5): 1602-1611. https://doi.org/10.1016/j.net.2020.11.003
DORA PSI
Siefman D, Hursin M, Schnabel G, Sjöstrand H
Development and application of marginal likelihood optimization for integral parameter adjustment
Annals of Nuclear Energy. 2021; 159: 108255 (10 pp.). https://doi.org/10.1016/j.anucene.2021.108255
DORA PSI
Sobes V, de Saint Jean C, Rochman D, Cabellos O, Holcomb A, Bauge E, et al.
WPEC Subgroup 44 computational inter-comparison exercise on correlations in nuclear data libraries
Annals of Nuclear Energy. 2021; 164: 108605 (9 pp.). https://doi.org/10.1016/j.anucene.2021.108605
DORA PSI
Solans V, Rochman D, Brazell C, Vasiliev A, Ferroukhi H, Pautz A
Optimisation of used nuclear fuel canister loading using a neural network and genetic algorithm
Neural Computing & Applications. 2021; 33: 16627-16639. https://doi.org/10.1007/s00521-021-06258-2
DORA PSI
Torres Delgado LA, Verma V, Montalvo C, Dokhane A, García-Berrocal A
Operational modal analysis for characterization of mechanical and thermal-hydraulic fluctuations in simulated neutron noise
Nuclear Engineering and Design. 2021; 373: 111017 (18 pp.). https://doi.org/10.1016/j.nucengdes.2020.111017
DORA PSI
Verma V, Chionis D, Dokhane A, Ferroukhi H
Studies of reactor noise response to vibrations of reactor internals and thermal-hydraulic fluctuations in PWRs
Annals of Nuclear Energy. 2021; 157: 108212 (19 pp.). https://doi.org/10.1016/j.anucene.2021.108212
DORA PSI
Ványi AS, Babcsány B, Böröczki ZI, Horváth A, Hursin M, Szieberth M, et al.
Steady-state neutronic measurements and comprehensive numerical analysis for the BME training reactor
Annals of Nuclear Energy. 2021; 155: 108144 (15 pp.). https://doi.org/10.1016/j.anucene.2021.108144
DORA PSI

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2020

Alhassan E, Rochman D, Sjöstrand H, Vasiliev A, Koning AJ, Ferroukhi H
Bayesian updating for data adjustments and multi-level uncertainty propagation within Total Monte Carlo
Annals of Nuclear Energy. 2020; 139: 107239 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107239
DORA PSI
Chionis D, Dokhane A, Belblidia L, Ferroukhi H, Girardin G, Pautz A
Development and verification of a methodology for neutron noise response to fuel assembly vibrations
Annals of Nuclear Energy. 2020; 147: 107669 (15 pp.). https://doi.org/10.1016/j.anucene.2020.107669
DORA PSI
Fiorina C, Scolaro A, Siefman D, Hursin M, Pautz A
Artificial neural networks as surrogate models for uncertainty quantification and data assimilation in 2-D/3-D fuel performance studies
Journal of Nuclear Engineering. 2020; 1(1): 54-62. https://doi.org/10.3390/jne1010005
DORA PSI
Guerrero C, Lerendegui-Marco J, Paul M, Tessler M, Heinitz S, Domingo-Pardo C, et al.
Neutron capture on the s-process branching point ¹⁷¹Tm via time-of-flight and activation
Physical Review Letters. 2020; 125(14): 142701 (8 pp.). https://doi.org/10.1103/PhysRevLett.125.142701
DORA PSI
Hursin M, Pakari O, Perret G, Frajtag P, Lamirand V, Pázsit I, et al.
Measurement of the gas velocity in a water-air mixture in CROCUS using neutron noise techniques
Nuclear Technology. 2020; 206(10): 1566-1583. https://doi.org/10.1080/00295450.2019.1701906
DORA PSI
Hursin M, Pelloni S, Vasiliev A, Ferroukhi H
Treatment of the implicit effect in Shark-X
Annals of Nuclear Energy. 2020; 138: 107178 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107178
DORA PSI
Khvostov G
Analysis of cladding failure in a BWR fuel rod using a SLICE-DO model of the FALCON code
Nuclear Engineering and Technology. 2020; 52(12): 2887-2900. https://doi.org/10.1016/j.net.2020.05.015
DORA PSI
Khvostov G
Analytical criteria for fuel fragmentation and burst FGR during a LOCA
Nuclear Engineering and Technology. 2020; 52(10): 2402-2409. https://doi.org/10.1016/j.net.2020.03.009
DORA PSI
Khvostov G
Numerical simulation of the effects of localized cladding oxidation on LWR fuel rod design limits using a SLICE-DO model of the FALCON code
Nuclear Engineering and Technology. 2020; 52(1): 135-147. https://doi.org/10.1016/j.net.2019.07.010
DORA PSI
Kim W, Hursin M, Pautz A, Vincent L, Pavel F, Lee D
Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor
Annals of Nuclear Energy. 2020; 136: 107034 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107034
DORA PSI
Konarski P, Cozzo C, Khvostov G, Ferroukhi H
Dry storage modeling activities at PSI: implementation and testing of a creep model for dry storage
Kerntechnik. 2020; 85(6): 419-425. https://doi.org/10.3139/124.200072
DORA PSI
Laureau A, Lamirand V, Rochman D, Pautz A
Uncertainty propagation based on correlated sampling technique for nuclear data applications
EPJ Nuclear Sciences and Technologies. 2020; 6: 8 (9 pp.). https://doi.org/10.1051/epjn/2020003
DORA PSI
Laureau A, Lamirand V, Rochman D, Pautz A
Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor
EPJ Nuclear Sciences and Technologies. 2020; 6: 9 (8 pp.). https://doi.org/10.1051/epjn/2020004
DORA PSI
Mala P, Pautz A
Development and verification of pin-by-pin homogenized simplified transport solver Tortin for PWR core analysis
Nuclear Engineering and Technology. 2020; 52(11): 2431-2441. https://doi.org/10.1016/j.net.2020.04.022
DORA PSI
Mazzone A, Cristallo S, Aberle O, Alaerts G, Alcayne V, Amaducci S, et al.
Measurement of the ¹⁵⁴Gd(n,γ) cross section and its astrophysical implications
Physics Letters, Section B: Nuclear, Elementary Particle and High-Energy Physics. 2020; 804: 135405 (6 pp.). https://doi.org/10.1016/j.physletb.2020.135405
DORA PSI
Mora DF, Costa Garrido O, Mukin R, Niffenegger M
Fracture mechanics analyses of a reactor pressure vessel under non-uniform cooling with a combined TRACE-XFEM approach
Engineering Fracture Mechanics. 2020; 238: 107258 (16 pp.). https://doi.org/10.1016/j.engfracmech.2020.107258
DORA PSI
Morató S, Bernal Á, Miró R, Roman JE, Verdú G
Calculation of λ modes of the multi-group neutron transport equation using the discrete ordinates and Finite Difference Method
Annals of Nuclear Energy. 2020; 137: 107077 (15 pp.). https://doi.org/10.1016/j.anucene.2019.107077
DORA PSI
Papadionysiou M, Seongchan K, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
Assessment of nTRACER and PARCS performance for VVER configurations
Nuclear Science and Engineering. 2020; 194(11): 1056-1066. https://doi.org/10.1080/00295639.2020.1753418
DORA PSI
Pelloni S, Rochman D
Resonance parameter adjustment in the resolved region based upon an Asymptotic Generalized Linear Least-Squares methodology in conjunction with the Monte Carlo method
Annals of Nuclear Energy. 2020; 145: 107509 (9 pp.). https://doi.org/10.1016/j.anucene.2020.107509
DORA PSI
Plompen AJM, Cabellos O, De Saint Jean C, Fleming M, Algora A, Angelone M, et al.
The joint evaluated fission and fusion nuclear data library, JEFF-3.3
European Physical Journal A: Hadrons and Nuclei. 2020; 56(7): 181 (108 pp.). https://doi.org/10.1140/epja/s10050-020-00141-9
DORA PSI
Rochman D, Koning AJ, Sublet J-C
A statistical analysis of evaluated neutron resonances with TARES for JEFF-3.3, JENDL-4.0, ENDF/B-VIII.0 and TENDL-2019
Nuclear Data Sheets. 2020; 163: 163-190. https://doi.org/10.1016/j.nds.2019.12.003
DORA PSI
Rochman D, Vasiliev A, Ferroukhi H, Seidl M, Basualdo J
Improvement of PIE analysis with a full core simulation: the U1 case

Annals of Nuclear Energy. 2020; 148: 107706 (11 pp.). https://doi.org/10.1016/j.anucene.2020.107706
DORA PSI
Rochman D, Dokhane A, Vasiliev A, Ferroukhi H, Hursin M
Nuclear data uncertainties for Swiss BWR spent nuclear fuel characteristics
European Physical Journal Plus. 2020; 135: 233 (18 pp.). https://doi.org/10.1140/epjp/s13360-020-00258-2
DORA PSI
Rochman D, Dokhane A, Vasiliev A, Ferroukhi H, Hursin M
Nuclear data uncertainties for core parameters based on Swiss BWR operated cycles
Annals of Nuclear Energy. 2020; 148: 107727 (8 pp.). https://doi.org/10.1016/j.anucene.2020.107727
DORA PSI
Rochman D, Vasiliev A, Ferroukhi H, Pecchia M
Optimization of Swiss used nuclear fuel canister for final repository: homogeneous vs. mixed loading
Annals of Nuclear Energy. 2020; 148: 107756 (8 pp.). https://doi.org/10.1016/j.anucene.2020.107756
DORA PSI
Scolaro A, Clifford I, Fiorina C, Pautz A
The OFFBEAT multi-dimensional fuel behavior solver
Nuclear Engineering and Design. 2020; 358: 110416 (16 pp.). https://doi.org/10.1016/j.nucengdes.2019.110416
DORA PSI
Siefman D, Hursin M, Perret G, Pautz A
Applying SHARK-X to perform data assimilation with the LWR-PROTEUS Phase II integral experiments
Progress in Nuclear Energy. 2020; 121: 103245 (9 pp.). https://doi.org/10.1016/j.pnucene.2020.103245
DORA PSI
Siefman D, Hursin M, Sjostrand H, Schnabel G, Rochman D, Pautz A
Data assimilation of post-irradiation examination data for fission yields from GEF
EPJ Nuclear Sciences and Technologies. 2020; 6: 52 (17 pp.). https://doi.org/10.1051/epjn/2020015
DORA PSI
Siefman D, Hursin M, Aufiero M, Bidaud A, Pautz A
On data assimilation with Monte-Carlo-calculated and statistically uncertain sensitivity coefficients
Annals of Nuclear Energy. 2020; 135: 106951 (13 pp.). https://doi.org/10.1016/j.anucene.2019.106951
DORA PSI
Solans V, Rochman D, Ferroukhi H, Vasiliev A, Pautz A
Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters
Nuclear Engineering and Design. 2020; 370: 110897 (11 pp.). https://doi.org/10.1016/j.nucengdes.2020.110897
DORA PSI
Vasiliev A, Grimm P, Ferroukhi H, Pecchia M, Ledergerber G
A comprehensive theoretical assessment of potential 'tramp uranium' isotopic evolution in BWR reactors
Annals of Nuclear Energy. 2020; 144: 107489 (11 pp.). https://doi.org/10.1016/j.anucene.2020.107489
DORA PSI
Vitullo F, Lamirand V, Mosset J-B, Frajtag P, Pakari O, Perret G, et al.
A mm³ fiber-coupled scintillator for in-core thermal neutron detection in CROCUS
IEEE Transactions on Nuclear Science. 2020; 67(4): 625-635. https://doi.org/10.1109/TNS.2020.2977530
DORA PSI
Wolfertz A, Adams R, Perret G
First tests of a gamma-blind fast neutron detector using a ZnS:Ag-epoxy mixture cast around wavelength-shifting fibers
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2020; 971: 164003 (9 pp.). https://doi.org/10.1016/j.nima.2020.164003
DORA PSI

Seidl M, Schillebeeckx P, Rochman D

On the potential to increase the accuracy of source term calculations for spent nuclear fuel from an industry perspective
atw Int. J. Nucl. Power. 2020:353-361.
DORA PSI

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2019

Chionis D, Dokhane A, Ferroukhi H, Pautz A
Application of causality analysis on nuclear reactor systems
Chaos: An Interdisciplinary Journal of Nonlinear Science. 2019; 29(4): 043126 (16 pp.). https://doi.org/10.1063/1.5083905
DORA PSI
Clifford I, Pecchia M, Mukin R, Cozzo C, Ferroukhi H, Gorzel A
Studies on the effects of local power peaking on heat transfer under dryout conditions in BWRs
Annals of Nuclear Energy. 2019; 130: 440-451. https://doi.org/10.1016/j.anucene.2019.03.017
DORA PSI
Griffin PJ, Koning AJ, Rochman D
Impact of nuclear data uncertainty in the modeling of neutron-induced recoil atom energy distributions in silicon
IEEE Transactions on Nuclear Science. 2019; 66(7): 1719-1729. https://doi.org/10.1109/TNS.2019.2894730
DORA PSI
Hennig D, Lange C, Rizwan-uddin, Dokhane A, Knospe A
Principles for the application of bifurcation theory for the systematic analysis of nuclear reactor stability, part1: theory
Progress in Nuclear Energy. 2019; 115: 231-249. https://doi.org/10.1016/j.pnucene.2019.02.009
DORA PSI
Hennig D, Rizwan-uddin, Lange C, Dokhane A, Knospe A
Principles for the application of bifurcation theory for the systematic analysis of nuclear reactor stability, part2: application
Progress in Nuclear Energy. 2019; 113: 263-280. https://doi.org/10.1016/j.pnucene.2019.01.009
DORA PSI
Koning AJ, Rochman D, Sublet J-C, Dzysiuk N, Fleming M, van der Marck S
TENDL: complete nuclear data library for innovative nuclear science and technology
Nuclear Data Sheets. 2019; 155: 1-55. https://doi.org/10.1016/j.nds.2019.01.002
DORA PSI
Nikitin K, Mueller P, Bruder A, Walser S, Judd J, Hiltbrand D
BWR-4 ATWS modeling with RELAP5-S3K
Nuclear Engineering and Design. 2019; 344: 38-45. https://doi.org/10.1016/j.nucengdes.2019.01.023
DORA PSI
Park J, Kim W, Hursin M, Perret G, Vasiliev A, Rochman D, et al.
Uncertainty quantification of LWR-PROTEUS Phase II experiments using CASMO-5
Annals of Nuclear Energy. 2019; 131: 9-22. https://doi.org/10.1016/j.anucene.2019.03.023
DORA PSI
Pecchia M, Ferroukhi H, Vasiliev A, Grimm P
Studies of intra-pin power distributions in operated BWR fuel assemblies using MCNP with a cycle check-up methodology
Annals of Nuclear Energy. 2019; 129: 67-78. https://doi.org/10.1016/j.anucene.2019.01.047
DORA PSI
Pelloni S, Rochman D
Enhancements along with application of the Asymptotic Progressing nuclear data Incremental Adjustment (APIA) methodology by individual assimilations of fast reactor data
Annals of Nuclear Energy. 2019; 129: 79-89. https://doi.org/10.1016/j.anucene.2019.01.057
DORA PSI
Perret G, Wicaksono D, Clifford ID, Ferroukhi H
Global sensitivity and registration strategy for temperature profile of reflood experiment simulations
Nuclear Technology. 2019; 205(12): 1638-1651. https://doi.org/10.1080/00295450.2019.1591154
DORA PSI
Puragliesi R
Assessment of a URANS CFD model for gravity driven flows: a comparison with OECD/PKL2 ROCOM experiments
Nuclear Engineering and Design. 2019; 356: 110365 (13 pp.). https://doi.org/10.1016/j.nucengdes.2019.110365
DORA PSI
Rochman D, Vasiliev A, Ferroukhi H, Pelloni S, Bauge E, Koning A
Correlation ν̅ _p– σ for U-Pu in the thermal and resonance neutron range via integral information
European Physical Journal Plus. 2019; 134: 453 (12 pp.). https://doi.org/10.1140/epjp/i2019-12875-7
DORA PSI
Shama A, Pouchon MA, Clifford I
Simulation of the microfluidic mixing and the droplet generation for 3D printing of nuclear fuels
Additive Manufacturing. 2019; 26: 1-14. https://doi.org/10.1016/j.addma.2018.12.011
DORA PSI
Skorek T, de Crécy A, Kovtonyuk A, Petruzzi A, Mendizábal R, de Alfonso E, et al.
Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes – PREMIUM benchmark
Nuclear Engineering and Design. 2019; 354: 110199 (23 pp.). https://doi.org/10.1016/j.nucengdes.2019.110199
DORA PSI
Sublet J-C, Bondarenko IP, Bonny G, Conlin JL, Gilbert MR, Greenwood LR, et al.
Neutron-induced damage simulations: beyond defect production cross-section, displacement per atom and iron-based metrics
European Physical Journal Plus. 2019; 134(7): 350 (50 pp.). https://doi.org/10.1140/epjp/i2019-12758-y
DORA PSI
Torres LA, Chionis D, Montalvo C, Dokhane A, García-Berrocal A
Neutron noise analysis of simulated mechanical and thermal-hydraulic perturbations in a PWR core
Annals of Nuclear Energy. 2019; 126: 242-252. https://doi.org/10.1016/j.anucene.2018.11.032
DORA PSI
Vasiliev A, Canepa S, Ferroukhi H, Boyarinov VF, Fomichenko PA, Joo HG, et al.
Cross-verification of SUHAM-TD and nTracer reactivity insertion transient solutions without materials homogenization approximation using OECD/NEA C5G7-TD benchmark
Annals of Nuclear Energy. 2019; 134: 235-243. https://doi.org/10.1016/j.anucene.2019.06.002
DORA PSI
Vasiliev A, Herrero J, Pecchia M, Rochman D, Ferroukhi H, Caruso S
Preliminary assessment of criticality safety constraints for swiss spent nuclear fuel loading in disposal canisters
Materials. 2019; 12(3): 494 (30 pp.). https://doi.org/10.3390/ma12030494
DORA PSI

Kromer H, Adams R, Soubelet B, Zboray R, Prasser H-M
Thermal analysis, design, and testing of a rotating beam target for a compact D-D fast neutron generator
Applied Radiation and Isotopes. 2019; 145: 47-54.
https://doi.org/10.1016/j.apradiso.2018.12.009
DORA PSI

Papini D, Andreani M, Steiner P, Ničeno B, Klügel J-U, Prasser H-M
Evaluation of the PAR mitigation system in Swiss PWR containment using the GOTHIC code
Nuclear Technology. 2019; 205(1-2): 153-173.
https://doi.org/10.1080/00295450.2018.1505356
DORA PSI

Soubelet B, Adams R, Kromer H, Zboray R, Prasser HM
Feasibility study of using a compact deuterium-deuterium (D-D) neutron generator for energy-selective transmission tomography
Radiation Physics and Chemistry. 2019; 156: 292-299.
https://doi.org/10.1016/j.radphyschem.2018.11.017
DORA PSI

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2018

Albiol T, Herranz L, Riera E, Dalibart C, Lind T, Del Corno A, et al.
Main results of the European PASSAM project on severe accident source term mitigation
Annals of Nuclear Energy. 2018; 116: 42-56. https://doi.org/10.1016/j.anucene.2018.02.024
DORA PSI
Andreani M, Paladino D, Papini D
Multi-step planning calculations with the GOTHIC code used for the design of complex experiments in the PANDA facility
Nuclear Engineering and Design. 2018; 339: 116-125. https://doi.org/10.1016/j.nucengdes.2018.09.005
DORA PSI
Badreddine H, Lafferty N, Ničeno B, Prasser H-M
Corrective interface tracking approach to simulate finite-size bubbly flows
Chemical Engineering Science. 2018; 178: 61-69. https://doi.org/10.1016/j.ces.2017.12.028
DORA PSI
Badreddine H, Ničeno B
Simulations of droplet merging with free surface and bubble column reactor with finite-size Lagrangian particle tracking
Chemical Engineering Science. 2018; 176: 609-621. https://doi.org/10.1016/j.ces.2017.10.037
DORA PSI
Bauge E, Rochman DA
Cross-observables and cross-isotopes correlations in nuclear data from integral constraints
EPJ Nuclear Sciences and Technologies. 2018; 4: 35 (6 pp.). https://doi.org/10.1051/epjn/2018011
DORA PSI
Beghi I, Lind T, Prasser H-M
Experimental studies on retention of iodine in a wet scrubber
Nuclear Engineering and Design. 2018; 326: 234-243. https://doi.org/10.1016/j.nucengdes.2017.11.025
DORA PSI
Bousbia Salah A, Ceuca SC, Puragliesi R, Mukin R, Grahn A, Kliem S, et al.
Unsteady single-phase natural-circulation flow mixing prediction using 3-D thermal-hydraulic system and CFD Codes
Nuclear Technology. 2018; 203(3): 293-314. https://doi.org/10.1080/00295450.2018.1461517
DORA PSI
Brown DA, Chadwick MB, Capote R, Kahler AC, Trkov A, Herman MW, et al.
ENDF/B-VIII.0: the 8^th major release of the nuclear reaction data library with CIELO-project cross sections, new standards and thermal scattering data
Nuclear Data Sheets. 2018; 148: 1-142. https://doi.org/10.1016/j.nds.2018.02.001
DORA PSI
Clifford I, Pecchia M, Puragliesi R, Vasiliev A, Ferroukhi H
On the characteristics of the flow and heat transfer in the core bypass region of a PWR
Nuclear Engineering and Design. 2018; 330: 117-128. https://doi.org/10.1016/j.nucengdes.2018.01.039
DORA PSI
Coindreau O, Jäckel B, Rocchi F, Alcaro F, Angelova D, Bandini G, et al.
Severe accident code-to-code comparison for two accident scenarios in a spent fuel pool
Annals of Nuclear Energy. 2018; 120: 880-887. https://doi.org/10.1016/j.anucene.2018.06.043
DORA PSI
Cozzo C, Rahman S
SiC cladding thermal conductivity requirements for normal operation and LOCA conditions
Progress in Nuclear Energy. 2018; 106: 278-283. https://doi.org/10.1016/j.pnucene.2018.03.016
DORA PSI
Dokhane A, Grandi G, Vasiliev A, Rochman D, Ferroukhi H
Validation of PSI best estimate plus uncertainty methodology against SPERT-III reactivity initiated accident experiments
Annals of Nuclear Energy. 2018; 118: 178-184. https://doi.org/10.1016/j.anucene.2018.04.022
DORA PSI
Dupont J, Mignot G, Paladino D, Prasser H-M
Mid wave infrared thermography of water films in condensing and evaporating environments
Nuclear Engineering and Design. 2018; 336: 80-89. https://doi.org/10.1016/j.nucengdes.2017.06.027
DORA PSI
Dzysiuk N, Koning AJ, Rochman D, Fischer U
Improving activation cross sections for fusion applications
Fusion Science and Technology. 2018; 73(1): 13-24. https://doi.org/10.1080/15361055.2017.1372682
DORA PSI
Fischer U, Angelone M, Avrigeanu M, Avrigeanu V, Bachmann C, Dzysiuk N, et al.
The role of nuclear data for fusion nuclear technology
Fusion Engineering and Design. 2018; 136: 162-167. https://doi.org/10.1016/j.fusengdes.2018.01.036
DORA PSI
Gallego-Marcos I, Kudinov P, Villanueva W, Kapulla R, Paranjape S, Paladino D, et al.
Pool stratification and mixing induced by steam injection through spargers: analysis of the PPOOLEX and PANDA experiments
Nuclear Engineering and Design. 2018; 337: 300-316. https://doi.org/10.1016/j.nucengdes.2018.07.004
DORA PSI
Gouëllo M, Kalilainen J, Kärkelä T, Auvinen A
Contribution to the understanding of iodine transport under primary circuit conditions: Csi/Cd and Csi/Ag interactions in condensed phase
Nuclear Materials and Energy. 2018; 17: 259-268. https://doi.org/10.1016/j.nme.2018.11.011
DORA PSI
Halouane Y, Dehbi A
CFD simulation of hydrogen mitigation by a passive autocatalytic recombiner
Nuclear Engineering and Design. 2018; 330: 488-496. https://doi.org/10.1016/j.nucengdes.2018.01.018
DORA PSI
Hursin M, Weiss C, Frajtag P, Lamirand V, Perret G, Kavrigin P, et al.
Testing of a sCVD diamond detection system in the CROCUS reactor
European Physical Journal A: Hadrons and Nuclei. 2018; 54(5): 82 (11 pp.). https://doi.org/10.1140/epja/i2018-12519-1
DORA PSI
Jo Y, Hursin M, Lee D, Ferroukhi H, Pautz A
Analysis of simplified BWR full core with serpent-2/simulate-3 hybrid stochastic/deterministic code
Annals of Nuclear Energy. 2018; 111: 141-151. https://doi.org/10.1016/j.anucene.2017.08.061
DORA PSI
Kapulla R, Mignot G, Paranjape S, Andreani M, Paladino D
Large scale experiments representing a containment natural circulation loop during an accident scenario
Science and Technology of Nuclear Installations. 2018; 2018: 8989070 (12 pp.). https://doi.org/10.1155/2018/8989070
DORA PSI
Kapulla R, Uong D, Zimmer C, Paladino D
PIV measurements in the vicinity of a steam sparger in the PANDA facility
Nuclear Engineering and Design. 2018; 336: 112-121. https://doi.org/10.1016/j.nucengdes.2017.07.003
DORA PSI
Khvostov G
Modeling of central void formation in LWR fuel pellets due to high-temperature restructuring
Nuclear Engineering and Technology. 2018; 50(7): 1190-1197. https://doi.org/10.1016/j.net.2018.07.003
DORA PSI
Khvostov G
Models for numerical simulation of burst FGR in fuel rods under the conditions of RIA
Nuclear Engineering and Design. 2018; 328: 36-57. https://doi.org/10.1016/j.nucengdes.2017.12.028
DORA PSI
Kim H, Dehbi A, Kalilainen J
Measurements and LES computations of a turbulent particle-laden flow inside a cubical differentially heated cavity
Atmospheric Environment. 2018; 186: 216-228. https://doi.org/10.1016/j.atmosenv.2018.05.037
DORA PSI
Marelli E, Villevieille C, Park S, Hérault N, Marino C
Co-Free P2–Na_0.67Mn_0.6Fe_0.25Al_0.15O₂ as promising cathode material for sodium-ion batteries
ACS Applied Energy Materials. 2018; 1(11): 5960-5967. https://doi.org/10.1021/acsaem.8b01015
DORA PSI
Mignot G, Dupont J, Paranjape S, Ouldrebai H, Bissels W-M, Paladino D, et al.
Measurement of liquid films thickness in a condensing and re-evaporating environment using attenuation of near infrared light
Nuclear Engineering and Design. 2018; 336: 64-73. https://doi.org/10.1016/j.nucengdes.2017.06.023
DORA PSI
Mukin R, Clifford I, Zerkak O, Ferroukhi H
Modeling and analysis of selected organization for economic cooperation and development PKL-3 station blackout experiments using TRACE
Nuclear Engineering and Technology. 2018; 50(3): 356-367. https://doi.org/10.1016/j.net.2017.12.005
DORA PSI
Mukin R, Puragliesi R, Pecchia M, Seidl M
Subchannel modeling of single rod bowing in a bundle geometry
Nuclear Engineering and Design. 2018; 340: 347-369. https://doi.org/10.1016/j.nucengdes.2018.09.032
DORA PSI
Noguere G, Tommasi J, Privas E, Schmidt K-H, Rochman D
Systematics of Nd cumulative fission yields for neutron-induced fission of ²³⁵U, ²³⁸U, ²³⁸Pu, ²³⁹Pu, ²⁴⁰Pu and ²⁴¹Pu
European Physical Journal Plus. 2018; 133(3): 99 (14 pp.). https://doi.org/10.1140/epjp/i2018-11926-y
DORA PSI
Pakari O, Lamirand V, Perret G, Frajtag P, Pautz A
Kinetic parameter measurements in the CROCUS reactor using current mode instrumentation
IEEE Transactions on Nuclear Science. 2018; 65(9): 2456-2460. https://doi.org/10.1109/TNS.2018.2831180
DORA PSI
Papadionysiou M, Perret G, Zboray R, Adams R, Mosset J-B
Monte Carlo simulation of a scintillation detector for spent fuel characterization in a hot cell
Nuclear Engineering and Design. 2018; 332: 119-126. https://doi.org/10.1016/j.nucengdes.2018.03.033
DORA PSI
Pelloni S, Rochman D
Cross-section adjustment in the fast energy range on the basis of an Asymptotic Progressing nuclear data Incremental Adjustment (APIA) methodology
Annals of Nuclear Energy. 2018; 115: 323-342. https://doi.org/10.1016/j.anucene.2018.01.037
DORA PSI
Pelloni S, Rochman D
Performance assessment of adjusted nuclear data along with their covariances on the basis of fast reactor experiments
Annals of Nuclear Energy. 2018; 121: 361-373. https://doi.org/10.1016/j.anucene.2018.07.043
DORA PSI
Qian G, Niffenegger M, Sharabi M, Lafferty N
Effect of non-uniform reactor cooling on fracture and constraint of a reactor pressure vessel
Fatigue and Fracture of Engineering Materials and Structures. 2018; 41(7): 1559-1575. https://doi.org/10.1111/ffe.12796
DORA PSI
Rahman S, Karanki DR, Epiney A, Wicaksono D, Zerkak O, Dang VN
Deterministic sampling for propagating epistemic and aleatory uncertainty in dynamic event tree analysis
Reliability Engineering and System Safety. 2018; 175: 62-78. https://doi.org/10.1016/j.ress.2018.03.009
DORA PSI
Rochman D, Vasiliev A, Ferroukhi H, Pecchia M
Consistent criticality and radiation studies of Swiss spent nuclear fuel: the CS₂M approach
Journal of Hazardous Materials. 2018; 357: 384-392. https://doi.org/10.1016/j.jhazmat.2018.05.041
DORA PSI
Rochman D, Vasiliev A, Ferroukhi H, Dokhane H, Koning A
How inelastic scattering stimulates nonlinear reactor core parameter behaviour
Annals of Nuclear Energy. 2018; 112: 236-244. https://doi.org/10.1016/j.anucene.2017.10.018
DORA PSI
Rochman D, Bauge E, Vasiliev A, Ferroukhi H, Pelloni S, Koning AJ, et al.
Monte Carlo nuclear data adjustment via integral information
European Physical Journal Plus. 2018; 133(12): 537. https://doi.org/10.1140/epjp/i2018-12361-x
DORA PSI
Rochman DA, Bauge E, Vasiliev A, Ferroukhi H, Perret G
Nuclear data correlation between different isotopes via integral information
EPJ Nuclear Sciences and Technologies. 2018; 4: 7 (10 pp.). https://doi.org/10.1051/epjn/2018006
DORA PSI
Rochman DA, Vasiliev A, Dokhane A, Ferroukhi H
Uncertainties for Swiss LWR spent nuclear fuels due to nuclear data
EPJ Nuclear Sciences and Technologies. 2018; 4: 6 (15 pp.). https://doi.org/10.1051/epjn/2018005
DORA PSI
Rýdl A, Fernandez-Moguel L, Lind T
Modeling of aerosol fission product scrubbing in experiments and in integral severe accident scenarios
Nuclear Technology. 2018; 205(5): 655-670. https://doi.org/10.1080/00295450.2018.1511213
DORA PSI
Siefman D, Hursin M, Rochman D, Pelloni S, Pautz A
Stochastic vs. sensitivity-based integral parameter and nuclear data adjustments
European Physical Journal Plus. 2018; 133(10): 429 (10 pp.). https://doi.org/10.1140/epjp/i2018-12303-8
DORA PSI
Simakov SP, Fischer U, Koning AJ, Konobeyev AY, Rochman DA
Iron NRT- and arc-displacement cross sections and their covariances
Nuclear Materials and Energy. 2018; 15: 244-248. https://doi.org/10.1016/j.nme.2018.05.006
DORA PSI
Sjöstrand H, Asquith N, Helgesson P, Rochman D, van der Marck S
Efficient use of Monte Carlo: the fast correlation coefficient
EPJ Nuclear Sciences and Technologies. 2018; 4: 15 (5 pp.). https://doi.org/10.1051/epjn/2018019
DORA PSI
Vasiliev A, Rochman D, Pecchia M, Ferroukhi H
On the options for incorporating nuclear data uncertainties in criticality safety assessments for LWR fuel
Annals of Nuclear Energy. 2018; 116: 57-68. https://doi.org/10.1016/j.anucene.2018.01.046
DORA PSI
Zboray R, Trtik P
800 fps neutron radiography of air-water two-phase flow
MethodsX. 2018; 5: 96-102. https://doi.org/10.1016/j.mex.2018.01.008
DORA PSI
Zboray R, Bolesch C, Prasser H-M
Development of neutron and X-ray imaging techniques for nuclear fuel bundle optimization
Nuclear Engineering and Design. 2018; 336: 24-33. https://doi.org/10.1016/j.nucengdes.2017.04.035
DORA PSI

Measurement of the radiative capture cross section of the s-process branching points 204Tl and 171Tm at the n_TOF facility (CERN)
N_TOF Collaboration including D. Rochman
EPJ Web of Conferences 178, 03004 (2018)
https://doi.org/10.1051/epjconf/201817803004

Technical note: On modeling central void formation in LWR fuel pellets due to hightemperature restructuring
G. Khvostov
Nuclear Engineering and Design
https://doi.org/10.1016/j.net.2018.07.003

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2017

Aures A, Bostelmann F, Hursin M, Leray O
Benchmarking and application of the state-of-the-art uncertainty analysis methods XSUSA and SHARK-X
Annals of Nuclear Energy. 2017; 101: 262-269. https://doi.org/10.1016/j.anucene.2016.11.025
DORA PSI
Badillo A, Andreani M
An exploratory work on the use of a Lagrangian-Eulerian model for simulating heat transfer of subchannels under reflooding conditions
Nuclear Engineering and Design. 2017; 321: 156-172. https://doi.org/10.1016/j.nucengdes.2016.11.031
DORA PSI
Badreddine H, Sato Y, Berger M, Ničeno B
A three-dimensional, immersed boundary, finite volume method for the simulation of incompressible heat transfer flows around complex geometries
International Journal of Chemical Engineering. 2017; 2017: 1726519 (14 pp.). https://doi.org/10.1155/2017/1726519
DORA PSI
Bocharov D, Chollet M, Krack M, Bertsch J, Grolimund D, Martin M, et al.
Analysis of the U L₃-edge X-ray absorption spectra in UO₂ using molecular dynamics simulations
Progress in Nuclear Energy. 2017; 94: 187-193. https://doi.org/10.1016/j.pnucene.2016.07.017
DORA PSI
Bubelis E, Tosello A, Pfrang W, Schikorr M, Mikityuk K, Panadero A-L, et al.
System codes benchmarking on a low sodium void effect SFR heterogeneous core under ULOF conditions
Nuclear Engineering and Design. 2017; 320: 325-345. https://doi.org/10.1016/j.nucengdes.2017.06.015
DORA PSI
Chollet M, Krsjak V, Cozzo C, Bertsch J
Positron annihilation spectroscopy study of lattice defects in non-irradiated doped and un-doped fuels
EPJ Nuclear Sciences and Technologies. 2017; 3: 3 (5 pp.). https://doi.org/10.1051/epjn/2016040
DORA PSI
Dehbi A, Kalilainen J, Lind T, Auvinen A
A large eddy simulation of turbulent particle-laden flow inside a cubical differentially heated cavity
Journal of Aerosol Science. 2017; 103: 67-82. https://doi.org/10.1016/j.jaerosci.2016.10.003
DORA PSI
Dokhane A, Judd J, Gajev I, Zerkak O, Ferroukhi H, Kozlowski T
Analysis of Oskarshamn-2 stability event using TRACE/SIMULATE-3K and comparison to TRACE/PARCS and SIMULATE-3K stand-alone
Annals of Nuclear Energy. 2017; 102: 190-199. https://doi.org/10.1016/j.anucene.2016.12.015
DORA PSI
Fiorina C, Hursin M, Pautz A
Extension of the GeN-Foam neutronic solver to SP₃ analysis and application to the CROCUS experimental reactor
Annals of Nuclear Energy. 2017; 101: 419-428. https://doi.org/10.1016/j.anucene.2016.11.042
DORA PSI
Giustini G, Walker SP, Sato Y, Niceno B
Computational fluid dynamics analysis of the transient cooling of the boiling surface at bubble departure
Journal of Heat Transfer. 2017; 139(9): 091501 (15 pp.). https://doi.org/10.1115/1.4036572
DORA PSI
Grimm P, Hursin M, Perret G, Siefman D, Ferroukhi H
Analysis of reactivity worths of burnt PWR fuel samples measured in LWR-PROTEUS Phase II using a CASMO-5 reflected-assembly model
Progress in Nuclear Energy. 2017; 101: 280-287. https://doi.org/10.1016/j.pnucene.2017.03.018
DORA PSI
Guo Z, Ngayam-Happy R, Krack M, Pautz A
Atomic-scale effects of chromium-doping on defect behaviour in uranium dioxide fuel
Journal of Nuclear Materials. 2017; 488: 160-172. https://doi.org/10.1016/j.jnucmat.2017.02.043
DORA PSI
Halouane Y, Dehbi A
CFD simulations of premixed hydrogen combustion using the Eddy Dissipation and the Turbulent Flame Closure models
International Journal of Hydrogen Energy. 2017; 42(34): 21990-22004. https://doi.org/10.1016/j.ijhydene.2017.07.075
DORA PSI
Helgesson P, Sjöstrand H, Koning AJ, Rydén J, Rochman D, Alhassan E, et al.
Combining Total Monte Carlo and Unified Monte Carlo: Bayesian nuclear data uncertainty quantification from auto-generated experimental covariances
Progress in Nuclear Energy. 2017; 96: 76-96. https://doi.org/10.1016/j.pnucene.2016.11.006
DORA PSI
Hursin M, Bogetic S, Dohkane A, Canepa S, Zerkak O, Ferroukhi H, et al.
Development and validation of a TRACE/PARCS core model of Leibstadt Kernkraftwerk cycle 19
Annals of Nuclear Energy. 2017; 101: 559-575. https://doi.org/10.1016/j.anucene.2016.11.001
DORA PSI
Karanki DR, Rahman S, Dang VN, Zerkak O
Epistemic and aleatory uncertainties in integrated deterministic and probabilistic safety assessment: tradeoff between accuracy and accident simulations
Reliability Engineering and System Safety. 2017; 162: 91-102. https://doi.org/10.1016/j.ress.2017.01.015
DORA PSI
Kelm S, Kapulla R, Allelein H-J
Erosion of a confined stratified layer by a vertical jet - detailed assessment of a CFD approach against the OECD/NEA PSI benchmark
Nuclear Engineering and Design. 2017; 312: 228-238. https://doi.org/10.1016/j.nucengdes.2016.09.014
DORA PSI
Kliem S, Kozmenkov Y, Hadek J, Perin Y, Fouquet F, Bernard F, et al.
Testing the NURESIM platform on a PWR main steam line break benchmark
Nuclear Engineering and Design. 2017; 321: 8-25. https://doi.org/10.1016/j.nucengdes.2017.05.028
DORA PSI
Kéri A, Dähn R, Krack M, Churakov SV
Combined XAFS spectroscopy and ab initio study on the characterization of iron incorporation by montmorillonite
Environmental Science and Technology. 2017; 51(18): 10585-10594. https://doi.org/10.1021/acs.est.7b01670
DORA PSI
Leray O, Ferroukhi H, Hursin M, Vasiliev A, Rochman D
Methodology for core analyses with nuclear data uncertainty quantification and application to Swiss PWR operated cycles
Annals of Nuclear Energy. 2017; 110: 547-559. https://doi.org/10.1016/j.anucene.2017.07.006
DORA PSI
Leray O, Fiorito L, Rochman D, Ferroukhi H, Stankovskiy A, Van den Eynde G
Uncertainty propagation of fission product yields to nuclide composition and decay heat for a PWR UO2 fuel assembly
Progress in Nuclear Energy. 2017; 101: 486-495. https://doi.org/10.1016/j.pnucene.2017.05.033
DORA PSI
Li J, Rochman D, Vasiliev A, Ferroukhi H, Herrero J, Pautz A, et al.
Bowing effects on isotopic concentrations for simplified PWR assemblies and full cores
Annals of Nuclear Energy. 2017; 110: 1023-1029. https://doi.org/10.1016/j.anucene.2017.08.022
DORA PSI
Li J, Rochman D, Herrero J, Vasiliev A, Ferroukhi H, Pautz A, et al.
UO₂ fuel pin bowing effects on isotopic concentrations
Annals of Nuclear Energy. 2017; 105: 361-368. https://doi.org/10.1016/j.anucene.2017.03.038
DORA PSI
Maxim F, Niceno B, Testino A, Ludwig C
The impact of sorbent geometry on the sulphur adsorption under supercritical water conditions: a numerical study
Biomass Conversion and Biorefinery. 2017; 7(4): 479-485. https://doi.org/10.1007/s13399-017-0265-7
DORA PSI
Paranjape S, Kapulla R, Mignot G, Paladino D
Parametric study on density stratification erosion caused by a horizontal steam jet interacting with a vertical plate obstruction
Nuclear Engineering and Design. 2017; 312: 351-360. https://doi.org/10.1016/j.nucengdes.2016.12.012
DORA PSI
Pecchia M, Vasiliev A, Ferroukhi H, Pautz A
A methodology for evaluating weighting functions using MCNP and its application to PWR ex-core analyses
Annals of Nuclear Energy. 2017; 105: 121-132. https://doi.org/10.1016/j.anucene.2017.03.008
DORA PSI
Pelloni S
Comparison of progressive incremental adjustment sequences for cross-section and variance/covariance data adjustment by analyzing fast-spectrum systems
Annals of Nuclear Energy. 2017; 106: 33-50. https://doi.org/10.1016/j.anucene.2017.03.040
DORA PSI
Perret G, Geslot B, Gruel A, Blaise P, Di-Salvo J, De Izarra G, et al.
Kinetic parameter measurements in the Minerve reactor
IEEE Transactions on Nuclear Science. 2017; 64(1): 724-734. https://doi.org/10.1109/TNS.2016.2637569
DORA PSI
Rochman D, Bauge E, Vasiliev A, Ferroukhi H
Correlation ν̅_p - σ - χ in the fast neutron range via integral information
EPJ Nuclear Sciences and Technologies. 2017; 3: 14 (8 pp.). https://doi.org/10.1051/epjn/2017009
DORA PSI
Rochman D, Leray O, Hursin M, Ferroukhi H, Vasiliev A, Aures A, et al.
Nuclear data uncertainties for typical LWR fuel assemblies and a simple reactor core
Nuclear Data Sheets. 2017; 139: 1-76. https://doi.org/10.1016/j.nds.2017.01.001
DORA PSI
Rochman D, Goriely S, Koning AJ, Ferroukhi H
Radiative neutron capture: Hauser Feshbach vs. statistical resonances
Physics Letters, Section B: Nuclear, Elementary Particle and High-Energy Physics. 2017; 764: 109-113. https://doi.org/10.1016/j.physletb.2016.11.018
DORA PSI
Sato Y, Niceno B
Large eddy simulation of upward co-current annular boiling flow using an interface tracking method
Nuclear Engineering and Design. 2017; 321: 69-81. https://doi.org/10.1016/j.nucengdes.2017.03.003
DORA PSI
Sato Y, Niceno B
Nucleate pool boiling simulations using the interface tracking method: boiling regime from discrete bubble to vapor mushroom region
International Journal of Heat and Mass Transfer. 2017; 105: 505-524. https://doi.org/10.1016/j.ijheatmasstransfer.2016.10.018
DORA PSI
Szijártó R, Badillo A, Ničeno B, Prasser H-M
Condensation models for the water-steam interface and the volume of fluid method
International Journal of Multiphase Flow. 2017; 93: 63-70. https://doi.org/10.1016/j.ijmultiphaseflow.2017.04.002
DORA PSI
Yin W, Krack M, Li X, Chen L, Liu L
Periodic continuum solvation model integrated with first-principles calculations for solid surfaces
Progress in Natural Science: Materials International. 2017; 27(2): 283-288. https://doi.org/10.1016/j.pnsc.2017.03.003
DORA PSI
Zboray R, Adams R, Kis Z
Fast neutron radiography and tomography at a 10 MW research reactor beamline
Applied Radiation and Isotopes. 2017; 119: 43-50. https://doi.org/10.1016/j.apradiso.2016.10.012
DORA PSI

SFCOMPO-2.0: An OECD NEA Database Of Spent Nuclear Fuel Isotopic Assays, Reactor Design Specifications, And Operating Data
F. Michel-Sendis, I. Gauld, J.S. Martinez, C. Alejano, M. Bossant, D. Boulanger, O. Cabellos, V. Chrapciak, J. Conde, I. Fast, M. Gren, K. Govers, M. Gysemans, V. Hannstein, F. Havlu, M. Hennebach, G. Hordosy, G. Ilas, R. Kilger, R. Mills, D. Mountford, P. Ortego, G. Radulescu, M. Rahimi, A. Ranta-Aho, K. RantamäKi, B. Ruprecht, N. Soppera, M. Stuke, K. Suyama, S. Tittelbach, C. Tore, S. Van Winckel, A. Vasiliev, T. Watanabe, Toru Yamamoto, Toshihisa Yamamoto
Annals of Nuclear Energy 110 (2017) 779 788
http://dx.doi.org/10.1016/j.anucene.2017.07.022

Modelling And Analysis Of Selected OECD PKL3 Station-Blackout Experiments Using TRACE
R. Mukin, I. Clifford, O. Zerkak, H. Ferroukhi
Nuclear Engineering and Technology, Net 473. (2017)
https://doi.org/10.1016/j.net.2017.12.005

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2016

Adams R, Zboray R, Prasser H-M
A novel fast-neutron tomography system based on a plastic scintillator array and a compact D-D neutron generator
Applied Radiation and Isotopes. 2016; 107: 1-7. https://doi.org/10.1016/j.apradiso.2015.09.002
DORA PSI
Adorni M, Herranz LE, Hollands T, Ahn K-II, Bals C, D'Auria F, et al.
OECD/NEA Sandia Fuel Project phase I: benchmark of the ignition testing
Nuclear Engineering and Design. 2016; 307: 418-430. https://doi.org/10.1016/j.nucengdes.2016.07.016
DORA PSI
Alhassan E, Sjöstrand H, Helgesson P, Österlund M, Pomp S, Koning AJ, et al.
On the use of integral experiments for uncertainty reduction of reactor macroscopic parameters within the TMC methodology
Progress in Nuclear Energy. 2016; 88: 43-52. https://doi.org/10.1016/j.pnucene.2015.11.015
DORA PSI
Alhassan E, Sjöstrand H, Helgesson P, Österlund M, Pomp S, Koning AJ, et al.
Selecting benchmarks for reactor simulations: an application to a lead fast reactor
Annals of Nuclear Energy. 2016; 96: 158-169. https://doi.org/10.1016/j.anucene.2016.05.033
DORA PSI
Andreani M, Badillo A, Kapulla R
Synthesis of the OECD/NEA-PSI CFD benchmark exercise
Nuclear Engineering and Design. 2016; 299: 59-80. https://doi.org/10.1016/j.nucengdes.2015.12.029
DORA PSI
Beuzet E, Haurais F, Bals C, Coindreau O, Fernandez-Moguel L, Vasiliev A, et al.
Cladding oxidation during air ingress. Part II: synthesis of modelling results
Annals of Nuclear Energy. 2016; 93: 18-27. https://doi.org/10.1016/j.anucene.2015.12.031
DORA PSI
Bozzetti C, Daellenbach KR, Hueglin C, Fermo P, Sciare J, Kasper-Giebl A, et al.
Size-resolved identification, characterization, and quantification of primary biological organic aerosol at a European rural site
Environmental Science and Technology. 2016; 50(7): 3425-3434. https://doi.org/10.1021/acs.est.5b05960
DORA PSI
Brankov V, Khvostov G, Mikityuk K, Pautz A, Restani R, Abolhassani S, et al.
Analysis of effects of pellet-cladding bonding on trapping of the released fission gases in high burnup KKL BWR fuels
Nuclear Engineering and Design. 2016; 305: 559-568. https://doi.org/10.1016/j.nucengdes.2016.06.021
DORA PSI
Brankov V, Khvostov G, Mikityuk K, Pautz A, Wiesenack W
Characterization of the relocated and dispersed fuel in the Halden reactor project LOCA tests based on gamma scan data
Nuclear Engineering and Design. 2016; 300: 97-106. https://doi.org/10.1016/j.nucengdes.2015.11.023
DORA PSI
Cozzo C, Ishizaki K, Pouchon MA, Vaucher S
Developing an in situ EXAFS experiment of microwave-induced gelation
Journal of Sol-Gel Science and Technology. 2016; 78(3): 507-513. https://doi.org/10.1007/s10971-016-3992-5
DORA PSI
Daellenbach KR, Bozzetti C, Křepelová A, Canonaco F, Wolf R, Zotter P, et al.
Characterization and source apportionment of organic aerosol using offline aerosol mass spectrometry
Atmospheric Measurement Techniques. 2016; 9(1): 23-39. https://doi.org/10.5194/amt-9-23-2016
DORA PSI
Dehbi A
A unified correlation for steam condensation rates in the presence of air-helium mixtures under naturally driven flows
Nuclear Engineering and Design. 2016; 300: 601-609. https://doi.org/10.1016/j.nucengdes.2016.02.009
DORA PSI
Dehbi A, Suckow D, Lind T, Guentay S, Danner S, Mukin R
Key findings from the artist project on aerosol retention in a dry steam generator
Nuclear Engineering and Technology. 2016; 48(4): 870-880. https://doi.org/10.1016/j.net.2016.06.001
DORA PSI
Dokhane A, Ferroukhi H, Pautz A
Validation studies and interpretation of the Oskarshamn-2 1999 stability event with SIMULATE-3K
Annals of Nuclear Energy. 2016; 96: 344-353. https://doi.org/10.1016/j.anucene.2016.06.016
DORA PSI
Dupont J, Mignot G, Zboray R, Prasser H-M
Infrared film thickness measurement: comparison with cold neutron imaging
Journal of Nuclear Science and Technology. 2016; 53(5): 673-681. https://doi.org/10.1080/00223131.2015.1102779
DORA PSI
Epiney A, Canepa S, Zerkak O, Ferroukhi H
Towards a consolidated approach for the assessment of evaluation models of nuclear power reactors
Nuclear Technology. 2016; 196(2): 223-237. https://doi.org/10.13182/NT16-47
DORA PSI
Fiorina C, Kerkar N, Mikityuk K, Rubiolo P, Pautz A
Development and verification of the neutron diffusion solver for the GeN-Foam multi-physics platform
Annals of Nuclear Energy. 2016; 96: 212-222. https://doi.org/10.1016/j.anucene.2016.05.023
DORA PSI
Froidevaux P, Bochud F, Baechler S, Castella V, Augsburger M, Bailat C, et al.
²¹⁰Po poisoning as possible cause of death: forensic investigations and toxicological analysis of the remains of Yasser Arafat
Forensic Science International. 2016; 259: 1-9. https://doi.org/10.1016/j.forsciint.2015.09.019
DORA PSI
González-Albuixech VF, Qian G, Sharabi M, Niffenegger M, Niceno B, Lafferty N
Coupled RELAP5, 3D CFD and FEM analysis of postulated cracks in RPVs subjected to PTS loading
Nuclear Engineering and Design. 2016; 297: 111-122. https://doi.org/10.1016/j.nucengdes.2015.11.032
DORA PSI
González-Albuixech VF, Qian G, Sharabi M, Niffenegger M, Niceno B, Lafferty N
Integrity analysis of a reactor pressure vessel subjected to a realistic pressurized thermal shock considering the cooling plume and constraint effects
Engineering Fracture Mechanics. 2016; 162: 201-217. https://doi.org/10.1016/j.engfracmech.2016.05.010
DORA PSI
Gu HF, Niceno B, Grundler PV, Sharabi M, Veleva L, Ritter S
Computational study of platinum nanoparticle deposition on the surfaces of crevices
Nuclear Engineering and Design. 2016; 304: 84-99. https://doi.org/10.1016/j.nucengdes.2016.04.020
DORA PSI
Helgesson P, Sjöstrand H, Koning AJ, Rydén J, Rochman D, Alhassan E, et al.
Sampling of systematic errors to estimate likelihood weights in nuclear data uncertainty propagation
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2016; 807: 137-149. https://doi.org/10.1016/j.nima.2015.10.024
DORA PSI
Herrero JJ, Vasiliev A, Pecchia M, Ferroukhi H, Caruso S
Review calculations for the OECD/NEA Burn-up Credit Criticality Safety Benchmark
Annals of Nuclear Energy. 2016; 87(P2): 48-57. https://doi.org/10.1016/j.anucene.2015.08.014
DORA PSI
Hursin M, Downar TJ, Yoon JI, Joo HG
Assessment of assembly homogenized two-steps core dynamic calculations using direct whole core transport solutions
Annals of Nuclear Energy. 2016; 87: 356-365. https://doi.org/10.1016/j.anucene.2015.09.015
DORA PSI
Hursin M, Scriven M, Perret G, Pautz A
Uncertainty quantification and representativity analysis of LWR-PROTEUS Phase III experiments using SHARKX
Annals of Nuclear Energy. 2016; 91: 48-58. https://doi.org/10.1016/j.anucene.2015.12.035
DORA PSI
Jayaraju ST, Roelofs F, Komen EMJ, Dehbi A
RANS modeling of fluid flow and dust deposition in nuclear pebble-beds
Nuclear Engineering and Design. 2016; 308: 222-237. https://doi.org/10.1016/j.nucengdes.2016.08.037
DORA PSI
Jäckel BS, Bevilacqua A, Ducros G, Gauntt R, Stuckert J
Land contamination activity data interpretation from Fukushima Daiichi accident
Nuclear Engineering and Design. 2016; 300: 28-33. https://doi.org/10.1016/j.nucengdes.2015.12.030
DORA PSI
Kalilainen J, Rantanen P, Lind T, Auvinen A, Dehbi A
Experimental investigation of a turbulent particle-laden flow inside a cubical differentially heated cavity
Journal of Aerosol Science. 2016; 100: 73-87. https://doi.org/10.1016/j.jaerosci.2016.06.001
DORA PSI
Khvostov G, Wiesenack W
Analysis of selected Halden overpressure tests using the FALCON code
Nuclear Engineering and Design. 2016; 310: 395-409. https://doi.org/10.1016/j.nucengdes.2016.10.033
DORA PSI
Leray O, Rochman D, Grimm P, Ferroukhi H, Vasiliev A, Hursin M, et al.
Nuclear data uncertainty propagation on spent fuel nuclide compositions
Annals of Nuclear Energy. 2016; 94: 603-611. https://doi.org/10.1016/j.anucene.2016.03.023
DORA PSI
Lindley BA, Fiorina C, Gregg R, Franceschini F, Parks GT
The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe – Part II: thorium fuel cycle
Progress in Nuclear Energy. 2016; 87: 144-155. https://doi.org/10.1016/j.pnucene.2014.11.016
DORA PSI
Mignot G, Paranjape S, Paladino D, Jaeckel B, Rydl A
Large scale experiments simulating hydrogen distribution in a spent fuel pool building during a hypothetical fuel uncovery accident scenario
Nuclear Engineering and Technology. 2016; 48(4): 881-892. https://doi.org/10.1016/j.net.2016.06.005
DORA PSI
Mukin RV
Bubble reconstruction method for wire-mesh sensors measurements
Experiments in Fluids. 2016; 57(8): 133 (12 pp.). https://doi.org/10.1007/s00348-016-2220-y
DORA PSI
Mukin R, Dehbi A
Particle deposition modeling in the secondary side of a steam generator bundle model
Nuclear Engineering and Design. 2016; 299: 112-123. https://doi.org/10.1016/j.nucengdes.2015.09.001
DORA PSI
Murallidharan J, Giustini G, Sato Y, Ničeno B, Badalassi V, Walker SP
Computational fluid dynamic simulation of single bubble growth under high-pressure pool boiling conditions
Nuclear Engineering and Technology. 2016; 48(4): 859-869. https://doi.org/10.1016/j.net.2016.06.004
DORA PSI
Paladino D, Andreani M, Guentay S, Mignot G, Kapulla R, Paranjape S, et al.
Outcomes from the EURATOM–ROSATOM ERCOSAM SAMARA projects on containment thermal-hydraulics for severe accident management
Nuclear Engineering and Design. 2016; 308: 103-114. https://doi.org/10.1016/j.nucengdes.2016.08.011
DORA PSI
Pecchia M, Wicaksono D, Grimm P, Vasiliev A, Perret G, Ferroukhi H, et al.
Validation of Monte Carlo based burnup codes against LWR-PROTEUS Phase-II experimental data
Annals of Nuclear Energy. 2016; 97: 153-164. https://doi.org/10.1016/j.anucene.2016.07.001
DORA PSI
Pellegrini M, Dolganov K, Herranz LE, Bonneville H, Luxat D, Sonnenkalb M, et al.
Benchmark study of the accident at the Fukushima Daiichi NPS: best-estimate case comparison
Nuclear Technology. 2016; 196(2): 198-210. https://doi.org/10.13182/NT16-63
DORA PSI
Perret G, Blaise P, Messaoudi N, Geslot B, Wagemans J, Baeten P, et al.
Validation of Monte-Carlo methods for generation time and delayed neutron fraction predictions
Annals of Nuclear Energy. 2016; 97: 165-170. https://doi.org/10.1016/j.anucene.2016.07.015
DORA PSI
Prasser H-M, Bolesch C, Cramer K, Ito D, Papadopoulos P, Saxena A, et al.
Bubbly, slug, and annular two-phase flow in tight-lattice subchannels
Nuclear Engineering and Technology. 2016; 48(4): 847-858. https://doi.org/10.1016/j.net.2016.06.007
DORA PSI
Puragliesi R, Zhou L, Zerkak O, Pautz A
Steady-state CFD simulations of an EPR^TM reactor pressure vessel: a validation study based on the JULIETTE experiments
Nuclear Engineering and Design. 2016; 300: 41-56. https://doi.org/10.1016/j.nucengdes.2015.12.025
DORA PSI
Qian G, González-Albuixech VF, Niffenegger M, Sharabi M
Probabilistic pressurized thermal shock analysis for a reactor pressure vessel considering plume cooling effect
Journal of Pressure Vessel Technology. 2016; 138(4): 041204 (8 pp.). https://doi.org/10.1115/1.4032197
DORA PSI
Rochman D, Leray O, Vasiliev A, Ferroukhi H, Koning AJ, Fleming M, et al.
A Bayesian Monte Carlo method for fission yield covariance information
Annals of Nuclear Energy. 2016; 95: 125-134. https://doi.org/10.1016/j.anucene.2016.05.005
DORA PSI
Rochman D, Vasiliev A, Ferroukhi H, Zhu T, van der Marck SC, Koning AJ
Nuclear data uncertainty for criticality-safety: Monte Carlo vs. linear perturbation
Annals of Nuclear Energy. 2016; 92: 150-160. https://doi.org/10.1016/j.anucene.2016.01.042
DORA PSI
Rochman D, Leray O, Perret G, Vasiliev A, Ferroukhi H, Koning AJ
Re-evaluation of the thermal neutron capture cross section of ¹⁴⁷Nd
Annals of Nuclear Energy. 2016; 94: 612-617. https://doi.org/10.1016/j.anucene.2016.03.024
DORA PSI
Rýdl A, Lind T, Birchley J
Integral analyses of fission product retention at mitigated thermally-induced SGTR using ARTIST experimental data
Nuclear Engineering and Design. 2016; 297: 175-187. https://doi.org/10.1016/j.nucengdes.2015.11.014
DORA PSI
Saxena A, Zboray R, Prasser H-M
Simulations and measurements of adiabatic annular flows in triangular, tight lattice nuclear fuel bundle model
Nuclear Engineering and Design. 2016; 299: 163-173. https://doi.org/10.1016/j.nucengdes.2015.07.063
DORA PSI
Sharabi M, González-Albuixech VF, Lafferty N, Niceno B, Niffenegger M
Computational fluid dynamics study of pressurized thermal shock phenomena in the reactor pressure vessel
Nuclear Engineering and Design. 2016; 299: 136-145. https://doi.org/10.1016/j.nucengdes.2015.10.014
DORA PSI
Stirling A, Rozgonyi T, Krack M, Bernasconi M
Prebiotic NH₃ Formation: Insights from Simulations
Inorganic Chemistry. 2016; 55(4): 1934-1939. https://doi.org/10.1021/acs.inorgchem.5b02911
DORA PSI
Takagi H, Nakashima M, Sato Y, Matsuuchi K, Sanders RH
Numerical and experimental investigations of human swimming motions
Journal of Sports Sciences. 2016; 34(16): 1564-1580. https://doi.org/10.1080/02640414.2015.1123284
DORA PSI
Vasiliev A, Rochman DI, Pecchia M, Ferroukhi H
Exploring stochastic sampling in nuclear data uncertainties assessment for reactor physics applications and validation studies
Energies. 2016; 9(12): 1039 (18 pp.). https://doi.org/10.3390/en9121039
DORA PSI
Vasiliev A, Ferroukhi H, Pecchia M, Pautz A
Localized neutron flux assessment and verification studies using MCNPX PWR full core model
Annals of Nuclear Energy. 2016; 92: 317-332. https://doi.org/10.1016/j.anucene.2016.01.026
DORA PSI
Wicaksono D, Zerkak O, Pautz A
Global sensitivity analysis of transient code output applied to a reflood experiment model using the TRACE code
Nuclear Science and Engineering. 2016; 184(3): 400-429. https://doi.org/10.13182/NSE16-37
DORA PSI
Yin W-J, Wen B, Bandaru S, Krack M, Lau MW, Liu L-M
The effect of excess electron and hole on CO₂ adsorption and activation on rutile (110) surface
Scientific Reports. 2016; 6: 23298 (9 pp.). https://doi.org/10.1038/srep23298
DORA PSI
Zhang Y, Mikityuk K
Static and transient analysis of a medium-sized sodium cooled fast reactor loaded with oxide, nitride, carbide and metallic fuels
Annals of Nuclear Energy. 2016; 87: 761-771. https://doi.org/10.1016/j.anucene.2015.03.025
DORA PSI
Zhu T, Vasiliev A, Ferroukhi H, Rochman D, Pautz A
Testing the sampling-based NUSS-RF tool for the nuclear data-related global sensitivity analysis with Monte Carlo neutronics calculations
Nuclear Science and Engineering. 2016; 184(1): 69-83. https://doi.org/10.13182/NSE14-142
DORA PSI

Steady-State CFD Simulations Of An Eprtm Reactor Pressure Vessel: A Validation Study Based On The Juliette Experiments
R. Puragliesi, L. Zhou, O. Zerkak, A. Pautz
Nuclear Engineering And Design, Vol. 300, Pp. 41 56 (2016)
http://dx.doi.org/10.1016/j.nucengdes.2015.12.025

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2015

Adams R, Bort L, Zboray R, Prasser H-M
Development and characterization of a D-D fast neutron generator for imaging applications
Applied Radiation and Isotopes. 2015; 96: 114-121. https://doi.org/10.1016/j.apradiso.2014.11.017
DORA PSI
Aufiero M, Bidaud A, Hursin M, Leppänen J, Palmiotti G, Pelloni S, et al.
A collision history-based approach to sensitivity/perturbation calculations in the continuous energy Monte Carlo code SERPENT
Annals of Nuclear Energy. 2015; 85: 245-258. https://doi.org/10.1016/j.anucene.2015.05.008
DORA PSI
Badreddine H, Sato Y, Niceno B, Prasser H-M
Finite size Lagrangian particle tracking approach to simulate dispersed bubbly flows
Chemical Engineering Science. 2015; 122: 321-335. https://doi.org/10.1016/j.ces.2014.09.037
DORA PSI
Becker H, Bison G, Blau B, Chowdhuri Z, Eikenberg J, Fertl M, et al.
Neutron production and thermal moderation at the PSI UCN source
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2015; 777: 20-27. https://doi.org/10.1016/j.nima.2014.12.091
DORA PSI
Bertolus M, Freyss M, Dorado B, Martin G, Hoang K, Maillard S, et al.
Linking atomic and mesoscopic scales for the modelling of the transport properties of uranium dioxide under irradiation
Journal of Nuclear Materials. 2015; 462: 475-495. https://doi.org/10.1016/j.jnucmat.2015.02.026
DORA PSI
Bosshard C, Deville MO, Dehbi A, Leriche E
UDNS or LES, that is the question
Open Journal of Fluid Dynamics. 2015; 5(4): 339-352. https://doi.org/10.4236/ojfd.2015.54034
DORA PSI
Dangendorf V, Zboray R
Potential and status in imaging with fast neutrons
Neutron News. 2015; 26(2): 27-30. https://doi.org/10.1080/10448632.2015.1028276
DORA PSI
Dehbi A
A generalized correlation for steam condensation rates in the presence of air under turbulent free convection
International Journal of Heat and Mass Transfer. 2015; 86: 11754 (15 pp.). https://doi.org/10.1016/j.ijheatmasstransfer.2015.02.034
DORA PSI
Demeshko M, Dokhane A, Washio T, Ferroukhi H, Kawahara Y, Aguirre C
Application of continuous and structural ARMA modeling for noise analysis of a BWR coupled core and plant instability event
Annals of Nuclear Energy. 2015; 75: 645-657. https://doi.org/10.1016/j.anucene.2014.08.045
DORA PSI
Dupont J, Mignot G, Prasser H-M
Two-dimensional mapping of falling water film thickness with near-infrared attenuation
Experiments in Fluids. 2015; 56(5): 90 (16 pp.). https://doi.org/10.1007/s00348-015-1955-1
DORA PSI
Dupré A, Vasiliev A, Ferroukhi H, Pautz A
Towards modeling and validation enhancements of the PSI MCNPX fast neutron fluence computational scheme based on recent PWR experimental data
Annals of Nuclear Energy. 2015; 85: 820-829. https://doi.org/10.1016/j.anucene.2015.06.040
DORA PSI
Fernandez-Moguel L, Birchley J
Analysis of the accident in the Fukushima Daiichi nuclear power station unit 3 with MELCOR_2.1
Annals of Nuclear Energy. 2015; 83: 193-215. https://doi.org/10.1016/j.anucene.2015.04.021
DORA PSI
Fernandez-Moguel L
Comparative assessment of PSI air oxidation model implementation in SCDAPSim3.5, MELCOR 1.8.6 and MELCOR 2.1
Annals of Nuclear Energy. 2015; 81: 134-142. https://doi.org/10.1016/j.anucene.2015.03.015
DORA PSI
Fiorina C, Clifford I, Aufiero M, Mikityuk K
GeN-Foam: A novel OpenFOAM^® based multi-physics solver for 2D/3D transient analysis of nuclear reactors
Nuclear Engineering and Design. 2015; 294: 24-37. https://doi.org/10.1016/j.nucengdes.2015.05.035
DORA PSI
Freixa J, Martínez-Quiroga V, Zerkak O, Reventós F
Modelling guidelines for core exit temperature simulations with system codes
Nuclear Engineering and Design. 2015; 286: 116-129. https://doi.org/10.1016/j.nucengdes.2015.02.003
DORA PSI
González-Albuixech VF, Qian G, Sharabi M, Niffenegger M, Niceno B, Lafferty N
Comparison of PTS analyses of RPVs based on 3D-CFD and RELAP5
Nuclear Engineering and Design. 2015; 291: 168-178. https://doi.org/10.1016/j.nucengdes.2015.05.025
DORA PSI
Hombourger BA, Křepel J, Mikityuk K, Pautz A
Parametric lattice study of a graphite-moderated molten salt reactor
Journal of Nuclear Engineering and Radiation Science. 2015; 1(1): 011009 (8 pp.). https://doi.org/10.1115/1.4026401
DORA PSI
Hursin M, Perret G, Pautz A
Verification of the new implementations in SHARKX against TSUNAMI to perform pinpower UQ and representativity analysis
Annals of Nuclear Energy. 2015; 77: 300-309. https://doi.org/10.1016/j.anucene.2014.11.019
DORA PSI
Jayaraju ST, Sathiah P, Roelofs F, Dehbi A
RANS modeling for particle transport and deposition in turbulent duct flows: near wall model uncertainties
Nuclear Engineering and Design. 2015; 289: 60-72. https://doi.org/10.1016/j.nucengdes.2015.04.011
DORA PSI
Jäckel BS
Status of the spent fuel in the reactor buildings of Fukushima Daiichi 1-4
Nuclear Engineering and Design. 2015; 283: 2-7. https://doi.org/10.1016/j.nucengdes.2014.07.007
DORA PSI
Karanki DR, Kim T-W, Dang VN
A dynamic event tree informed approach to probabilistic accident sequence modeling: dynamics and variabilities in medium LOCA
Reliability Engineering and System Safety. 2015; 142: 78-91. https://doi.org/10.1016/j.ress.2015.04.011
DORA PSI
Krack M
On the ground state electronic structure of uranium dioxide
Physica Scripta. 2015; 90(9): 094014 (7 pp.). https://doi.org/10.1088/0031-8949/90/9/094014
DORA PSI
Lal S, Sato Y, Niceno B
Direct numerical simulation of bubble dynamics in subcooled and near-saturated convective nucleate boiling
International Journal of Heat and Fluid Flow. 2015; 51: 16-28. https://doi.org/10.1016/j.ijheatfluidflow.2014.10.018
DORA PSI
Lindley BA, Fiorina C, Gregg R, Franceschini F, Parks GT
The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe - part I: uranium fuel cycle
Progress in Nuclear Energy. 2015; 85: 498-510. https://doi.org/10.1016/j.pnucene.2015.07.020
DORA PSI
Ngayam-Happy R, Krack M, Pautz A
Effects of stoichiometry on the defect clustering in uranium dioxide
Journal of Physics: Condensed Matter. 2015; 27(45): 455401 (13 pp.). https://doi.org/10.1088/0953-8984/27/45/455401
DORA PSI
Nikitin E, Fridman E, Mikityuk K
On the use of the SPH method in nodal diffusion analyses of SFR cores
Annals of Nuclear Energy. 2015; 85: 544-551. https://doi.org/10.1016/j.anucene.2015.06.007
DORA PSI
Nikitin E, Fridman E, Mikityuk K
Solution of the OECD/NEA neutronic SFR benchmark with Serpent-DYN3D and Serpent-PARCS code systems
Annals of Nuclear Energy. 2015; 75: 492-497. https://doi.org/10.1016/j.anucene.2014.08.054
DORA PSI
Pecchia M, Vasiliev A, Leray O, Ferroukhi H, Pautz A
Advanced calculation methodology for manufacturing and technological parameters' uncertainties propagation at arbitrary level of lattice elements grouping
Journal of Nuclear Science and Technology. 2015; 52(7-8): 1084-1092. https://doi.org/10.1080/00223131.2015.1032382
DORA PSI
Pecchia M, Parisi C, D'Auria F, Mazzantini O
Application of MCNP for predicting power excursion during LOCA in Atucha-2 PHWR
Annals of Nuclear Energy. 2015; 85: 271-278. https://doi.org/10.1016/j.anucene.2015.05.023
DORA PSI
Pecchia M, Vasiliev A, Ferroukhi H, Pautz A
Criticality safety evaluation of a Swiss wet storage pool using a global uncertainty analysis methodology
Annals of Nuclear Energy. 2015; 83: 226-235. https://doi.org/10.1016/j.anucene.2015.03.052
DORA PSI
Perkó Z, Pelloni S, Mikityuk K, Křepel J, Szieberth M, Gaëtan G, et al.
Core neutronics characterization of the GFR2400 gas cooled fast reactor
Progress in Nuclear Energy. 2015; 83: 460-481. https://doi.org/10.1016/j.pnucene.2014.09.016
DORA PSI
Pucciarelli A, Borroni I, Sharabi M, Ambrosini W
Results of 4-equation turbulence models in the prediction of heat transfer to supercritical pressure fluids
Nuclear Engineering and Design. 2015; 281: 5-14. https://doi.org/10.1016/j.nucengdes.2014.11.004
DORA PSI
Rais A, Siefman D, Girardin G, Hursin M, Pautz A
Methods and models for the coupled neutronics and thermal-hydraulics analysis of the CROCUS reactor at EFPL
Science and Technology of Nuclear Installations. 2015; 2015: 237646 (9 pp.). https://doi.org/10.1155/2015/237646
DORA PSI
Ribeiro F, Khvostov G
Multi-scale approach to advanced fuel modelling for enhanced safety
Progress in Nuclear Energy. 2015; 84: 24-35. https://doi.org/10.1016/j.pnucene.2015.03.022
DORA PSI
Rochman D, Koning AJ, van der Marck SC
Improving neutronics simulations and uncertainties via a selection of nuclear data
European Physical Journal A: Hadrons and Nuclei. 2015; 51(12): 182 (11 pp.). https://doi.org/10.1140/epja/i2015-15182-0
DORA PSI
Salazar G, Zhang YL, Agrios K, Szidat S
Development of a method for fast and automatic radiocarbon measurement of aerosol samples by online coupling of an elemental analyzer with a MICADAS AMS
Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms. 2015; 361: 163-167. https://doi.org/10.1016/j.nimb.2015.03.051
DORA PSI
Sato Y, Niceno B
A depletable micro-layer model for nucleate pool boiling
Journal of Computational Physics. 2015; 300: 20-52. https://doi.org/10.1016/j.jcp.2015.07.046
DORA PSI
Siefman DJ, Girardin G, Rais A, Pautz A, Hursin M
Full core modeling techniques for research reactors with irregular geometries using Serpent and PARCS applied to the CROCUS reactor
Annals of Nuclear Energy. 2015; 85: 434-443. https://doi.org/10.1016/j.anucene.2015.05.004
DORA PSI
Stirling A, Rozgonyi T, Krack M, Bernasconi M
Pyrite in contact with supercritical water: the desolation of steam
Physical Chemistry Chemical Physics. 2015; 17(26): 17375-17379. https://doi.org/10.1039/c5cp01146a
DORA PSI
Yin W-J, Krack M, Wen B, Ma S-Y, Liu L-M
CO₂ capture and conversion on rutile TiO₂(110) in the water environment: insight by first-principles calculations
Journal of Physical Chemistry Letters. 2015; 6(13): 2538-2545. https://doi.org/10.1021/acs.jpclett.5b00798
DORA PSI
Zanetti M, Cammi A, Fiorina C, Luzzi L
A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics
Progress in Nuclear Energy. 2015; 83: 82-98. https://doi.org/10.1016/j.pnucene.2015.02.014
DORA PSI
Zboray R, Mignot G, Kapulla R, Paladino D
Erosion and break-up of light-gas layers by a horizontal jet in a multi-vessel, large-scale containment test system
Nuclear Engineering and Design. 2015; 291: 10-18. https://doi.org/10.1016/j.nucengdes.2015.05.006
DORA PSI
Zboray R, Dangendorf V, Mor I, Bromberger B, Tittelmeier K
Time-resolved fast-neutron radiography of air-water two-phase flows in a rectangular channel by an improved detection system
Review of Scientific Instruments. 2015; 86(7): 075103 (10 pp.). https://doi.org/10.1063/1.4926999
DORA PSI
Zerkak O, Kozlowski T, Gajev I
Review of multi-physics temporal coupling methods for analysis of nuclear reactors
Annals of Nuclear Energy. 2015; 84: 225-233. https://doi.org/10.1016/j.anucene.2015.01.019
DORA PSI
Zhu T, Vasiliev A, Ferroukhi H, Pautz A, Tarantola S
NUSS-RF: stochastic sampling-based tool for nuclear data sensitivity and uncertainty quantification
Journal of Nuclear Science and Technology. 2015; 52(7-8): 1000-1007. https://doi.org/10.1080/00223131.2015.1040864
DORA PSI
Zhu T, Vasiliev A, Ferroukhi H, Pautz A
NUSS: a tool for propagating multigroup nuclear data covariances in pointwise ACE-formatted nuclear data using stochastic sampling method
Annals of Nuclear Energy. 2015; 75: 713-722. https://doi.org/10.1016/j.anucene.2014.09.013
DORA PSI

A Dynamic Event Tree Informed Approach To Probabilistic Accident Sequence Modeling: Dynamics And Variabilities In Medium LOCA
D.R. Karanki, T-W. Kim, V.N. Dang
Reliability Engineering And System Safety, Vol. 142, Pp. 78 91 (2015)
http://dx.doi.org/10.1016/j.ress.2015.04.011

Gen-Foam: A Novel Openfoam Based Multi-Physics Solver FOR2d/3d Transient Analysis Of Nuclear Reactors
C. Fiorina, I. Clifford, M. Aufiero, K. Mikityuk
Nuclear Engineering And Design, Vol. 294, Pp. 24-37, (2015)

Boron Dilution Transient Simulation Analyses In A PWR With Neutronics/Thermal-Hydraulics Coupled Codes In The NURISP Project
G. Jimenez, J.J. Herrero, A. Gommlich, S. Kliem, D. Cuervo, J. Jimenez
Annals of Nuclear Energy Vol. 84, Pp. 86-97 (2015)

Review Of Multi-Physics Temporal Coupling Methods For Analysis Of Nuclear Reactors
O. Zerkak, T. Kozlowski, I. Gajev
Annals of Nuclear Energy Vol. 84, Pp. 225-233 (2015)

Modelling Guidelines For Core Exit Temperature Simulations With System Codes
J. Freixa V. MartíNez-Quiroga, O. Zerkak, F. ReventóS
Nuclear Engineering and Design, Vol. 286, Pp. 116-129 (2015)

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2010 - 2014

Adams R, Zboray R, Cortesi M, Prasser H-M
Conceptual design and optimization of a plastic scintillator array for 2D tomography using a compact D-D fast neutron generator
Applied Radiation and Isotopes. 2014; 86: 63-70. https://doi.org/10.1016/j.apradiso.2014.01.001
DORA PSI
Apanasevich P, Coste P, Ničeno B, Heib C, Lucas D
Comparison of CFD simulations on two-phase pressurized thermal shock scenarios
Nuclear Engineering and Design. 2014; 266: 112-128. https://doi.org/10.1016/j.nucengdes.2013.10.023
DORA PSI
Bosshard C, Dehbi A, Deville M, Leriche E, Soldati A
Large eddy simulation of particulate flow inside a differentially heated cavity
Nuclear Engineering and Design. 2014; 267: 154-163. https://doi.org/10.1016/j.nucengdes.2013.12.035
DORA PSI
Cortesi M, Dangendorf V, Zboray R, Prasser H-M
A novel fast-neutron detector concept for energy-selective imaging and imaging spectroscopy
Review of Scientific Instruments. 2014; 85(7): 073305 (8 pp.). https://doi.org/10.1063/1.4890392
DORA PSI
Cozzo C, Orlov A, Borca C, Degueldre C
X-ray absorption in plutonium uranium mixed oxide fuel: thorium characterization
Progress in Nuclear Energy. 2014; 72: 91-95. https://doi.org/10.1016/j.pnucene.2013.09.009
DORA PSI
Cripps RC, Güntay S, Jäckel B
The predicted effects of selected Phebus FPT1 sump constituents on iodine volatility
Nuclear Engineering and Design. 2014; 272: 99-108. https://doi.org/10.1016/j.nucengdes.2014.02.019
DORA PSI
Dokhane A, Ferroukhi H, Pautz A
On out-of-phase higher mode oscillations with rotation and oscillation of symmetry line using an advanced integral stability methodology
Annals of Nuclear Energy. 2014; 67: 21-30. https://doi.org/10.1016/j.anucene.2013.11.006
DORA PSI
Draksler M, Ničeno B, Končar B, Cizelj L
Large eddy simulation of multiple impinging jets in hexagonal configuration - mean flow characteristics
International Journal of Heat and Fluid Flow. 2014; 46: 147-157. https://doi.org/10.1016/j.ijheatfluidflow.2014.01.005
DORA PSI
Fernandez-Moguel L, Bals C, Beuzet E, Bratfisch C, Coindreau O, Hózer Z, et al.
SARNET2 benchmark on air ingress experiments QUENCH-10, -16
Annals of Nuclear Energy. 2014; 74: 12-23. https://doi.org/10.1016/j.anucene.2014.05.013
DORA PSI
Ferroukhi H, Leray O, Hursin M, Vasiliev A, Perret G, Pautz A
Study of nuclear decay data contribution to uncertainties in heat load estimations for spent fuel pools
Nuclear Data Sheets. 2014; 118: 498-501. https://doi.org/10.1016/j.nds.2014.04.117
DORA PSI
Geža V, Milenković RŽ, Kapulla R, Dementjevs S, Jakovičs A, Wohlmuther M
Computational and experimental studies of the flow field near the beam entrance window of a liquid metal target
Nuclear Engineering and Design. 2014; 275: 96-106. https://doi.org/10.1016/j.nucengdes.2014.04.022
DORA PSI
Grasso G, Petrovich C, Mattioli D, Artioli C, Sciora P, Gugiu D, et al.
The core design of ALFRED, a demonstrator for the European lead-cooled reactors
Nuclear Engineering and Design. 2014; 278: 287-301. https://doi.org/10.1016/j.nucengdes.2014.07.032
DORA PSI
Hursin M, Collins B, Xu Y, Downar T
The development and implementation of a one-dimensional S_n method in the 2D-1D integral transport solution
Nuclear Science and Engineering. 2014; 176(2): 186-200. https://doi.org/10.13182/NSE12-4
DORA PSI
Kapulla R, Mignot G, Paranjape S, Ryan L, Paladino D
Large scale gas stratification erosion by a vertical helium-air jet
Science and Technology of Nuclear Installations. 2014; 2014: 197267 (16 pp.). https://doi.org/10.1155/2014/197267
DORA PSI
Křepel J, Hombourger B, Fiorina C, Mikityuk K, Rohde U, Kliem S, et al.
Fuel cycle advantages and dynamics features of liquid fueled MSR
Annals of Nuclear Energy. 2014; 64: 380-397. https://doi.org/10.1016/j.anucene.2013.08.007
DORA PSI
Lazaro A, Schikorr M, Mikityuk K, Ammirabile L, Bandini G, Darmet G, et al.
Code assessment and modelling for design basis accident analysis of the European sodium fast reactor design. Part II: optimised core and representative transients analysis
Nuclear Engineering and Design. 2014; 277: 265-276. https://doi.org/10.1016/j.nucengdes.2014.02.029
DORA PSI
Lindley BA, Fiorina C, Franceschini F, Lahoda EJ, Parks GT
Thorium breeder and burner fuel cycles in reduced-moderation LWRs compared to fast reactors
Progress in Nuclear Energy. 2014; 77: 107-123. https://doi.org/10.1016/j.pnucene.2014.06.010
DORA PSI
Lázaro A, Ammirabile L, Bandini G, Darmet G, Massara S, Dufour P, et al.
Code assessment and modelling for design basis accident analysis of the European sodium fast reactor design. Part I: system description, modelling and benchmarking
Nuclear Engineering and Design. 2014; 266: 1-16. https://doi.org/10.1016/j.nucengdes.2013.10.019
DORA PSI
Lüley J, Vrban B, Čerba Š, Haščík J, Nečas V, Pelloni S
Sensitivity and uncertainty analysis of the GFR MOX fuel subassembly
Nuclear Data Sheets. 2014; 118: 545-547. https://doi.org/10.1016/j.nds.2014.04.130
DORA PSI
Martin G, Garcia P, Sabathier C, Devynck F, Krack M, Maillard S
A thermal modelling of displacement cascades in uranium dioxide
Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms. 2014; 327: 108-112. https://doi.org/10.1016/j.nimb.2013.09.043
DORA PSI
Miyata H, Orihara H, Sato Y
Nonlinear ship waves and computational fluid dynamics
Proceedings of the Japan Academy Series B: Physical and Biological Sciences. 2014; 90(8): 278-300. https://doi.org/10.2183/pjab.90.278
DORA PSI
Mukin RV
Modeling of bubble coalescence and break-up in turbulent bubbly flow
International Journal of Multiphase Flow. 2014; 62: 52-66. https://doi.org/10.1016/j.ijmultiphaseflow.2014.02.008
DORA PSI
Ngayam-Happy R, Krack M
Investigation of the influence of off-stoichiometry on the radiation damage evolution in uranium dioxide
Progress in Nuclear Energy. 2014; 72: 38-43. https://doi.org/10.1016/j.pnucene.2013.09.015
DORA PSI
Papini D, Adamsson C, Andreani M, Prasser H-M
Assessment of GOTHIC and TRACE codes against selected PANDA experiments on a Passive Containment Condenser
Nuclear Engineering and Design. 2014; 278: 542-557. https://doi.org/10.1016/j.nucengdes.2014.08.007
DORA PSI
Papini D, Colombo M, Cammi A, Ricotti ME
Experimental and theoretical studies on density wave instabilities in helically coiled tubes
International Journal of Heat and Mass Transfer. 2014; 68: 343-356. https://doi.org/10.1016/j.ijheatmasstransfer.2013.09.035
DORA PSI
Pelloni S
Application of an iterative methodology for cross-section and variance/covariance data adjustment to the analysis of fast spectrum systems accounting for non-linearity
Annals of Nuclear Energy. 2014; 72: 373-390. https://doi.org/10.1016/j.anucene.2014.06.002
DORA PSI
Salvatores M, Palmiotti G, Aliberti G, Archier P, De Saint Jean C, Dupont E, et al.
Methods and issues for the combined use of integral experiments and covariance data: results of a NEA international collaborative study
Nuclear Data Sheets. 2014; 118: 38-71. https://doi.org/10.1016/j.nds.2014.04.005
DORA PSI
Szijártó R, Freixa J, Prasser H-M
Simulation of condensation in a closed, slightly inclined horizontal pipe with a modified RELAP5 code
Nuclear Engineering and Design. 2014; 273: 288-297. https://doi.org/10.1016/j.nucengdes.2014.03.028
DORA PSI
Toggweiler M, Adelmann A, Arbenz P, Yang J
A novel adaptive time stepping variant of the Boris-Buneman integrator for the simulation of particle accelerators with space charge
Journal of Computational Physics. 2014; 273: 255-267. https://doi.org/10.1016/j.jcp.2014.05.008
DORA PSI
Vasiliev A, Ferroukhi H, Zhu T, Pautz A
Nuclear data library effects on fast to thermal flux shapes around PWR control rod tips
Nuclear Data Sheets. 2014; 118: 575-578. https://doi.org/10.1016/j.nds.2014.04.139
DORA PSI
Vasiliev A, Wieselquist W, Ferroukhi H, Canepa S, Heldt J, Ledergerber G
Validation studies of computational scheme for high-fidelity fluence estimations of the Swiss BWRs
Progress in Nuclear Science and Technology. 2014; 4: 99-103. https://doi.org/10.15669/pnst.4.99
DORA PSI
Zboray R, Adams R, Cortesi M, Prasser H-M
Development of a fast neutron imaging system for investigating two-phase flows in nuclear thermal-hydraulic phenomena: a status report
Nuclear Engineering and Design. 2014; 273: 10-23. https://doi.org/10.1016/j.nucengdes.2014.01.027
DORA PSI
Zboray R, Mor I, Dangendorf V, Stark M, Tittelmeier K, Cortesi M, et al.
High-frame rate imaging of two-phase flow in a thin rectangular channel using fast neutrons
Applied Radiation and Isotopes. 2014; 90: 122-131. https://doi.org/10.1016/j.apradiso.2014.03.023
DORA PSI
Zhu T, Vasiliev A, Ferroukhi H, Pautz A
Application of the PSI-NUSS tool for the estimation of nuclear data related k_eff uncertainties for the OECD/NEA WPNCS UACSA Phase I benchmark
Nuclear Data Sheets. 2014; 118: 453-455. https://doi.org/10.1016/j.nds.2014.04.104
DORA PSI
Zhu T, Rochman D, Vasiliev A, Ferroukhi H, Wieselquist W, Pautz A
Comparison of two approaches for nuclear data uncertainty propagation in MCNPX for selected fast spectrum critical benchmarks
Nuclear Data Sheets. 2014; 118: 388-391. https://doi.org/10.1016/j.nds.2014.04.088
DORA PSI
Bosshard C, Dehbi A, Deville M, Leriche E, Puragliesi R, Soldati A
Large eddy simulation of the differentially heated cubic cavity flow by the spectral element method
Computers and Fluids. 2013; 86: 210-227. https://doi.org/10.1016/j.compfluid.2013.07.007
DORA PSI
Chawla R, Rätz D, Jordan KA, Perret G
Analysis of pin removal experiments conducted in a supercritical light water reactor-like test lattice
Nuclear Technology. 2013; 183(3): 321-330. https://doi.org/10.13182/NT13-A19421
DORA PSI
Cortesi M, Zboray R, Kaestner A, Prasser H-M
Development of a cold-neutron imaging detector based on thick gaseous electron multiplier
Review of Scientific Instruments. 2013; 84(2): 023305 (7 pp.). https://doi.org/10.1063/1.4793225
DORA PSI
Cortesi M, Zboray R, Adams R, Dangendorf V, Meshkian M, Prasser H-M
Development of large-area THGEM detectors for investigation of thermal-hydraulic phenomena using neutron imaging
Journal of Instrumentation. 2013; 8(10): C10009 (11 pp.). https://doi.org/10.1088/1748-0221/8/10/C10009
DORA PSI
Cortesi M, Zboray R, Adams R, Dangendorf V, Breskin A, Mayer S, et al.
First studies of electron transport along small gas gaps of novel foil radiation converters for fast-neutron detectors
Journal of Instrumentation. 2013; 8(1): P01016 (19 pp.). https://doi.org/10.1088/1748-0221/8/01/P01016
DORA PSI
Dehbi A, Badreddine H
CFD prediction of mixing in a steam generator mock-up: comparison between full geometry and porous medium approaches
Annals of Nuclear Energy. 2013; 58: 178-187. https://doi.org/10.1016/j.anucene.2013.03.019
DORA PSI
Dehbi A
On the adequacy of wall functions to predict condensation rates from steam-noncondensable gas mixtures
Nuclear Engineering and Design. 2013; 265: 25-34. https://doi.org/10.1016/j.nucengdes.2013.07.014
DORA PSI
Dehbi A, Janasz F, Bell B
Prediction of steam condensation in the presence of noncondensable gases using a CFD-based approach
Nuclear Engineering and Design. 2013; 258: 199-210. https://doi.org/10.1016/j.nucengdes.2013.02.002
DORA PSI
Dhotre MT, Deen NG, Niceno B, Khan Z, Joshi JB
Large eddy simulation for dispersed bubbly flows: a review
International Journal of Chemical Engineering. 2013; 2013: 343276 (22 pp.). https://doi.org/10.1155/2013/343276
DORA PSI
Dokhane A, Canepa S, Ferroukhi H
Transition to CASMO-5M and SIMULATE-3K for stability analyses of the Swiss boiling water reactors
Nuclear Technology. 2013; 183(3): 341-353. https://doi.org/10.13182/NT13-A19423
DORA PSI
Fernandez-Moguel L, Birchley J
Analysis of QUENCH-10 and -16 air ingress experiments with SCDAPSim3.5
Annals of Nuclear Energy. 2013; 53: 202-212. https://doi.org/10.1016/j.anucene.2012.08.030
DORA PSI
Fiorina C, Krepel J, Cammi A, Franceschini F, Mikityuk K, Ricotti ME
Analysis of thorium and uranium fuel cycles in an iso-breeder lead fast reactor using extended-EQL3D procedure
Annals of Nuclear Energy. 2013; 53: 492-506. https://doi.org/10.1016/j.anucene.2012.09.004
DORA PSI
Fiorina C, Aufiero M, Cammi A, Franceschini F, Krepel J, Luzzi L, et al.
Investigation of the MSFR core physics and fuel cycle characteristics
Progress in Nuclear Energy. 2013; 68: 153-168. https://doi.org/10.1016/j.pnucene.2013.06.006
DORA PSI
Freixa J, Kim T-W, Manera A
Post-test thermal-hydraulic analysis of two intermediate LOCA tests at the ROSA facility including uncertainty evaluation
Nuclear Engineering and Design. 2013; 264: 153-160. https://doi.org/10.1016/j.nucengdes.2013.02.023
DORA PSI
Giust FD, Grimm P, Chawla R
Experimental validation of 3-D reconstructed pin power distributions in full-scale BWR fuel assemblies with partial-length rods
Nuclear Science and Engineering. 2013; 175(3): 292-307. https://doi.org/10.13182/NSE12-69
DORA PSI
Hursin M, Downar TJ, Montgomery R
Impact of improved neutronic methodology on the cladding response during a PWR reactivity initiated accident
Nuclear Engineering and Design. 2013; 262: 180-188. https://doi.org/10.1016/j.nucengdes.2013.04.023
DORA PSI
Khvostov G, Lyon W, Zimmermann MA
Application of the FALCON code to PCI induced cladding failure and the effects of missing pellet surface
Annals of Nuclear Energy. 2013; 62: 398-412. https://doi.org/10.1016/j.anucene.2013.07.002
DORA PSI
Kröhnert H, Perret G, Murphy MF, Chawla R
Gamma-ray spectrometric measurements of fission rate ratios between fresh and burnt fuel following irradiation in a zero-power reactor
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2013; 698: 72-80. https://doi.org/10.1016/j.nima.2012.09.008
DORA PSI
Ngayam-Happy R, Becquart CS, Domain C
First principle-based AKMC modelling of the formation and medium-term evolution of point defect and solute-rich clusters in a neutron irradiated complex Fe-CuMnNiSiP alloy representative of reactor pressure vessel steels
Journal of Nuclear Materials. 2013; 440(1-3): 143-152. https://doi.org/10.1016/j.jnucmat.2013.04.081
DORA PSI
Ničeno B, Sharabi M
Large eddy simulation of turbulent heat transfer at supercritical pressures
Nuclear Engineering and Design. 2013; 261: 44-55. https://doi.org/10.1016/j.nucengdes.2013.03.042
DORA PSI
Ničeno B, Reiterer F, Ylönen A, Prasser H-M
Simulation of single-phase mixing in fuel rod bundles, using an immersed boundary method
Physica Scripta. 2013; T155: 014054 (13 pp.). https://doi.org/10.1088/0031-8949/2013/T155/014054
DORA PSI
Rabone J, Krack M
A procedure for bypassing metastable states in local basis set DFT+U calculations and its application to uranium dioxide surfaces
Computational Materials Science. 2013; 71: 157-164. https://doi.org/10.1016/j.commatsci.2013.01.023
DORA PSI
Rycroft CH, Dehbi A, Lind T, Güntay S
Granular flow in pebble-bed nuclear reactors: scaling, dust generation, and stress
Nuclear Engineering and Design. 2013; 265: 69-84. https://doi.org/10.1016/j.nucengdes.2013.07.010
DORA PSI
Sato Y, Hino T
A computational fluid dynamics analysis of hydrodynamic force acting on a swimmer's hand in a swimming competition
Journal of Sports Science and Medicine. 2013; 12(4): 679-689.
DORA PSI
Sato Y, Ničeno B
A sharp-interface phase change model for a mass-conservative interface tracking method
Journal of Computational Physics. 2013; 249: 127-161. https://doi.org/10.1016/j.jcp.2013.04.035
DORA PSI
Sato Y, Hino T, Ohashi K
Parallelization of an unstructured Navier-Stokes solver using a multi-color ordering method for OpenMP
Computers and Fluids. 2013; 88: 496-509. https://doi.org/10.1016/j.compfluid.2013.10.008
DORA PSI
Sun K, Krepel J, Mikityuk K, Chawla R
A neutronics study for improving the safety and performance parameters of a 3600 MWth Sodium-cooled Fast Reactor
Annals of Nuclear Energy. 2013; 53: 464-475. https://doi.org/10.1016/j.anucene.2012.10.004
DORA PSI
Sun K, Chenu A, Krepel J, Mikityuk K, Chawla R
Coupled 3-D neutronics/thermal-hydraulics optimization study for improving the response of a 3600 MW(thermal) SFR core to an unprotected loss-of-flow accident
Nuclear Technology. 2013; 183(3): 484-503. https://doi.org/10.13182/NT13-A19436
DORA PSI
Tenchine D, Pialla D, Fanning TH, Thomas JW, Chellapandi P, Shvetsov Y, et al.
International benchmark on the natural convection test in Phenix reactor
Nuclear Engineering and Design. 2013; 258: 189-198. https://doi.org/10.1016/j.nucengdes.2013.02.010
DORA PSI
Wieselquist W, Zhu T, Vasiliev A, Ferroukhi H
PSI methodologies for nuclear data uncertainty propagation with CASMO-5M and MCNPX: results for OECD/NEA UAM benchmark phase I
Science and Technology of Nuclear Installations. 2013; 2013: 549793 (15 pp.). https://doi.org/10.1155/2013/549793
DORA PSI
Yang JJ, Adelmann A, Barletta W, Calabretta L, Calanna A, Campo D, et al.
Beam dynamics simulation for the high intensity DAEδALUS cyclotrons
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2013; 704: 84-91. https://doi.org/10.1016/j.nima.2012.12.050
DORA PSI
Zboray R, Prasser H-M
Measuring liquid film thickness in annular two-phase flows by cold neutron imaging
Experiments in Fluids. 2013; 54(9): 1596 (15 pp.). https://doi.org/10.1007/s00348-013-1596-1
DORA PSI
Zboray R, Prasser H-M
Neutron imaging of annular flows in a tight lattice fuel bundle model
Nuclear Engineering and Design. 2013; 262: 589-599. https://doi.org/10.1016/j.nucengdes.2013.06.005
DORA PSI
Zboray R, Prasser H-M
Optimizing the performance of cold-neutron tomography for investigating annular flows and functional spacers in fuel rod bundles
Nuclear Engineering and Design. 2013; 260: 188-203. https://doi.org/10.1016/j.nucengdes.2013.03.026
DORA PSI
Ammar Y, Dehbi A, Reeks MW
Break-up of aerosol agglomerates in highly turbulent gas flow
Flow, Turbulence and Combustion. 2012; 89(3): 465-489. https://doi.org/10.1007/s10494-012-9398-8
DORA PSI
Andreani M, Bittermann D, Marsault P, Antoni O, Keresztúri A, Schlagenhaufer M, et al.
Evaluation of a preliminary safety concept for the HPLWR
Progress in Nuclear Energy. 2012; 55: 68-77. https://doi.org/10.1016/j.pnucene.2011.11.004
DORA PSI
Andreani M, Kapulla R, Zboray R
Gas stratification break-up by a vertical jet: simulations using the GOTHIC code
Nuclear Engineering and Design. 2012; 249: 71-81. https://doi.org/10.1016/j.nucengdes.2011.06.004
DORA PSI
Aounallah Y
Simulation of HALDEN IFA-650 loss-of-coolant accidents tests with TRACE
Kerntechnik. 2012; 77(5): 316-323. https://doi.org/10.3139/124.110214
DORA PSI
Badillo A
Quantitative phase-field modeling for boiling phenomena
Physical Review E. 2012; 86(4): 41603. https://doi.org/10.1103/PhysRevE.86.041603
DORA PSI
Birchley J, Fernandez-Moguel L
Simulation of air oxidation during a reactor accident sequence: part 1 - phenomenology and model development
Annals of Nuclear Energy. 2012; 40(1): 163-170. https://doi.org/10.1016/j.anucene.2011.10.019
DORA PSI
Chenu A, Adams R, Mikityuk K, Chawla R
Analysis of selected Phenix EOL tests with the FAST code system - part I: control-rod-shift experiments
Annals of Nuclear Energy. 2012; 49: 182-190. https://doi.org/10.1016/j.anucene.2012.05.036
DORA PSI
Chenu A, Mikityuk K, Chawla R
Analysis of selected Phenix EOL tests with the FAST code system - part II: unprotected phase of the Natural Convection Test
Annals of Nuclear Energy. 2012; 49: 191-199. https://doi.org/10.1016/j.anucene.2012.05.035
DORA PSI
Cortesi M, Zboray R, Adams R, Dangendorf V, Prasser H-M
Concept of a novel fast neutron imaging detector based on THGEM for fan-beam tomography applications
Journal of Instrumentation. 2012; 7(2): C02056 (11 pp.). https://doi.org/10.1088/1748-0221/7/02/C02056
DORA PSI
Devynck F, Iannuzzi M, Krack M
Frenkel pair recombinations in UO₂: importance of explicit description of polarizability in core-shell molecular dynamics simulations
Physical Review B. 2012; 85(18): 184103 (12 pp.). https://doi.org/10.1103/PhysRevB.85.184103
DORA PSI
Dietler R, Hursin M, Perret G, Jordan K, Chawla R
A novel design approach for a neutron measurement station for burnt fuel
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2012; 693: 59-66. https://doi.org/10.1016/j.nima.2012.07.009
DORA PSI
Epiney A, Alpy N, Mikityuk K, Chawla R
A standalone decay heat removal device for the Gas-cooled Fast Reactor for intermediate to atmospheric pressure conditions
Nuclear Engineering and Design. 2012; 242: 267-284. https://doi.org/10.1016/j.nucengdes.2011.10.011
DORA PSI
Fernandez-Moguel L, Birchley J
Simulation of air oxidation during a reactor accident sequence: part 2 - analysis of PARAMETER-SF4 air ingress experiment using RELAP5/SCDAPSIM
Annals of Nuclear Energy. 2012; 40(1): 141-152. https://doi.org/10.1016/j.anucene.2011.10.018
DORA PSI
Freixa J, Manera A
Remarks on consistent development of plant nodalizations: An example of application to the ROSA integral test facility
Science and Technology of Nuclear Installations. 2012; 2012: 158617. https://doi.org/10.1155/2012/158617
DORA PSI
Freixa J, Kim T-W, Manera A
Thermal-hydraulic analysis of an intermediate LOCA test at the ROSA facility including uncertainty evaluation
Nuclear Engineering and Design. 2012; 249: 97-103. https://doi.org/10.1016/j.nucengdes.2011.08.061
DORA PSI
Kapulla R, Mignot G, Paladino D
Large-scale containment cooler performance experiments under accident conditions
Science and Technology of Nuclear Installations. 2012; 2012: 943197 (20 pp.). https://doi.org/10.1155/2012/943197
DORA PSI
Kim T, Petrov V, Manera A, Lo S
Analysis of void fraction distribution and departure from nucleate boiling in single subchannel and bundle geometries using subchannel, system, and computational fluid dynamics codes
Science and Technology of Nuclear Installations. 2012; 2012: 746467. https://doi.org/10.1155/2012/746467
DORA PSI
Kim TW, Dang VN, Zimmermann MA, Manera A
Quantitative evaluation of change in core damage frequency by postulated power uprate: medium-break loss-of-coolant-accidents
Annals of Nuclear Energy. 2012; 47: 69-80. https://doi.org/10.1016/j.anucene.2012.04.021
DORA PSI
Kozmenkov Y, Rohde U, Manera A
Validation of the RELAP5 code for the modeling of flashing-induced instabilities under natural-circulation conditions using experimental data from the CIRCUS test facility
Nuclear Engineering and Design. 2012; 243: 168-175. https://doi.org/10.1016/j.nucengdes.2011.10.053
DORA PSI
Krepel J, Pelloni S, Mikityuk K
Comparison of open and closed U-Pu equilibrium fuel cycles for Generation-IV fast reactors with the EQL3D procedure
Nuclear Engineering and Design. 2012; 250: 392-402. https://doi.org/10.1016/j.nucengdes.2012.06.004
DORA PSI
Marinoni A, Girardin G, Mikityuk K
Analysis of the BN-600 fast-spectrum core mock-up at BFS-2 zero-power facility using MCNPX
Annals of Nuclear Energy. 2012; 44: 26-33. https://doi.org/10.1016/j.anucene.2012.01.011
DORA PSI
Paladino D, Dreier J
PANDA: A multipurpose integral test facility for LWR safety investigations
Science and Technology of Nuclear Installations. 2012; 2012: 239319. https://doi.org/10.1155/2012/239319
DORA PSI
Paladino D, Dreier J
Passive Containment Cooling System (PCCS) response with Drywell Gas Recirculation System (DGRS) activated during a severe accident scenario with release of non-condensable gas
Nuclear Engineering and Design. 2012; 247: 212-220. https://doi.org/10.1016/j.nucengdes.2012.03.006
DORA PSI
Paladino D, Andreani M, Zboray R, Dreier J
Toward a CFD-grade database addressing LWR containment phenomena
Nuclear Engineering and Design. 2012; 253: 331-342. https://doi.org/10.1016/j.nucengdes.2011.08.064
DORA PSI
Papini D, Cammi A, Colombo M, Ricotti ME
Time-domain linear and non-linear studies on density wave oscillations
Chemical Engineering Science. 2012; 81: 118-139. https://doi.org/10.1016/j.ces.2012.06.005
DORA PSI
Perret G, Jordan KA
On the combination of delayed neutron and delayed gamma measurement techniques for nuclear fuel and its application to nuclear data uncertainty reduction
IEEE Transactions on Nuclear Science. 2012; 59(6): 3166-3172. https://doi.org/10.1109/TNS.2012.2215339
DORA PSI
Rätz D, Jordan KA, Bayard A-SP, Perret G, Chawla R
Experimental investigation of moderator density variation effects in an SCWR-like fuel lattice
Nuclear Engineering and Design. 2012; 247: 236-247. https://doi.org/10.1016/j.nucengdes.2012.02.011
DORA PSI
Sato Y, Ničeno B
A conservative local interface sharpening scheme for the constrained interpolation profile method
International Journal for Numerical Methods in Fluids. 2012; 70(4): 441-467. https://doi.org/10.1002/fld.2695
DORA PSI
Sato Y, Ničeno B
A new contact line treatment for a conservative level set method
Journal of Computational Physics. 2012; 231(10): 3887-3895. https://doi.org/10.1016/j.jcp.2012.01.034
DORA PSI
Sharabi M, Freixa J
Analysis of the ISP-50 direct vessel injection sbloca in the atlas facility with the relap5/mod3.3 code
Nuclear Engineering and Technology. 2012; 44(7): 709-718. https://doi.org/10.5516/NET.02.2012.712
DORA PSI
Studer E, Brinster J, Tkatschenko I, Mignot G, Paladino D, Andreani M
Interaction of a light gas stratified layer with an air jet coming from below: large scale experiments and scaling issues
Nuclear Engineering and Design. 2012; 253: 406-412. https://doi.org/10.1016/j.nucengdes.2012.10.009
DORA PSI
Bertolotto D, Manera A, Macián-Juan R, Chawla R
Improvement of the one-dimensional dissolved-solute convection equation using the QUICKEST-ULTIMATE algorithm
Nuclear Engineering and Design. 2011; 241(1): 245-256. https://doi.org/10.1016/j.nucengdes.2010.10.021
DORA PSI
Caravati S, Colleoni D, Mazzarello R, Kühne TD, Krack M, Bernasconi M, et al.
First-principles study of nitrogen doping in cubic and amorphous Ge₂Sb₂Te₅
Journal of Physics: Condensed Matter. 2011; 23(26): 265801 (13 pp.). https://doi.org/10.1088/0953-8984/23/26/265801
DORA PSI
Chauliac C, Aragonés J-M, Bestion D, Cacuci DG, Crouzet N, Weiss F-P, et al.
NURESIM - A European simulation platform for nuclear reactor safety: Multi-scale and multi-physics calculations, sensitivity and uncertainty analysis
Nuclear Engineering and Design. 2011; 241(9): 3416-3426. https://doi.org/10.1016/j.nucengdes.2010.09.040
DORA PSI
Chenu A, Mikityuk K, Chawla R
Pressure drop modeling and comparisons with experiments for single- and two-phase sodium flow
Nuclear Engineering and Design. 2011; 241(9): 3898-3909. https://doi.org/10.1016/j.nucengdes.2011.07.009
DORA PSI
Chylarecka D, Kim TK, Tarafder K, Müller K, Gödel K, Czekaj I, et al.
Indirect magnetic coupling of manganese porphyrin to a ferromagnetic cobalt substrate
Journal of Physical Chemistry C. 2011; 115(4): 1295-1301. https://doi.org/10.1021/jp106822s
DORA PSI
Cripps RC, Jäckel B, Güntay S
On the radiolysis of iodide, nitrate and nitrite ions in aqueous solution: An experimental and modelling study
Nuclear Engineering and Design. 2011; 241(8): 3333-3347. https://doi.org/10.1016/j.nucengdes.2011.06.031
DORA PSI
Cripps RC, Güntay S, Jäckel B
The PSIodine Code: A computer program to model experimental data on iodine and other species in irradiated CsI solutions sparged with argon, air, or nitrous oxide
Nuclear Engineering and Design. 2011; 241(10): 4306-4325. https://doi.org/10.1016/j.nucengdes.2011.08.010
DORA PSI
Dehbi A, Martin S
CFD simulation of particle deposition on an array of spheres using an Euler/Lagrange approach
Nuclear Engineering and Design. 2011; 241(8): 3121-3129. https://doi.org/10.1016/j.nucengdes.2011.05.031
DORA PSI
Dehbi A, de Crécy F
Validation of the Langevin particle dispersion model against experiments on turbulent mixing in a T-junction
Powder Technology. 2011; 206(3): 312-321. https://doi.org/10.1016/j.powtec.2010.09.036
DORA PSI
Erkan N, Kapulla R, Mignot G, Zboray R, Paladino D
Experimental investigation of spray induced gas stratification break-up and mixing in two interconnected vessels
Nuclear Engineering and Design. 2011; 241(9): 3935-3944. https://doi.org/10.1016/j.nucengdes.2011.07.025
DORA PSI
Freixa J, Manera A
Verification of a TRACE EPR™ model on the basis of a scaling calculation of an SBLOCA ROSA test
Nuclear Engineering and Design. 2011; 241(3): 888-896. https://doi.org/10.1016/j.nucengdes.2010.12.016
DORA PSI
Froideval A, Badillo A, Bertsch J, Churakov S, Dähn R, Degueldre C, et al.
Towards possible opportunities in nuclear materials science and technology at an X-ray free electron laser research facility
Journal of Nuclear Materials. 2011; 416(1-2): 242-251. https://doi.org/10.1016/j.jnucmat.2011.01.124
DORA PSI
Giust FD, Grimm P, Chawla R
Experimental comparisons of 3D reconstructed pin-power distributions in full-scale BWR fuel assemblies
Journal of Engineering for Gas Turbines and Power. 2011; 133(5): 52909 (13 pp.). https://doi.org/10.1115/1.4002823
DORA PSI
Herranz LE, Vallejo I, Khvostov G, Sercombe J, Zhou G
Assessment of fuel rod performance codes under ramp scenarios investigated within the SCIP project
Nuclear Engineering and Design. 2011; 241(3): 815 (11 pp.)-825. https://doi.org/10.1016/j.nucengdes.2011.01.007
DORA PSI
Jordan KA, Perret G
A delayed neutron technique for measuring induced fission rates in fresh and burnt LWR fuel
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2011; 634(1): 91-100. https://doi.org/10.1016/j.nima.2011.01.064
DORA PSI
Khvostov G, Mikityuk K, Zimmermann MA
A model for fission gas release and gaseous swelling of the uranium dioxide fuel coupled with the FALCON code
Nuclear Engineering and Design. 2011; 241(8): 2983-3007. https://doi.org/10.1016/j.nucengdes.2011.06.020
DORA PSI
Khvostov G, Wiesenack W, Zimmermann MA, Ledergerber G
Some insights into the role of axial gas flow in fuel rod behaviour during the LOCA based on Halden tests and calculations with the FALCON-PSI code
Nuclear Engineering and Design. 2011; 241(5): 1500-1507. https://doi.org/10.1016/j.nucengdes.2011.03.003
DORA PSI
Kickhofel JL, Zboray R, Damsohn M, Kaestner A, Lehmann EH, Prasser HM
Cold neutron tomography of annular coolant flow in a double subchannel model of a boiling water reactor
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2011; 651(1): 297-304. https://doi.org/10.1016/j.nima.2011.01.062
DORA PSI
Kolbe E, Vasiliev A, Ferroukhi H
Assessment of the JEFF-3.1.1 neutron data library for CSE of LWR fuel storage pools
Journal of the Korean Physical Society. 2011; 59(23): 1174-1178. https://doi.org/10.3938/jkps.59.1174
DORA PSI
Lind T, Dehbi A, Güntay S
Aerosol retention in the flooded steam generator bundle during SGTR
Nuclear Engineering and Design. 2011; 241(1): 357-365. https://doi.org/10.1016/j.nucengdes.2010.10.025
DORA PSI
Mikityuk K, Shestopalov A
FRED fuel behaviour code: Main models and analysis of Halden IFA-503.2 tests
Nuclear engineering and design. 2011; 241(7): 2455-2461. https://doi.org/10.1016/j.nucengdes.2011.04.033
DORA PSI
Nikitin K, Manera A
Analysis of an ADS spurious opening event at a BWR/6 by means of the TRACE code
Nuclear Engineering and Design. 2011; 241(6): 2240-2247. https://doi.org/10.1016/j.nucengdes.2011.03.021
DORA PSI
Paladino D, Auban O, Huggenberger M, Dreier J
A PANDA integral test on the effect of light gas on a passive containment cooling system (PCCS)
Nuclear Engineering and Design. 2011; 241(11): 4551-4561. https://doi.org/10.1016/j.nucengdes.2010.11.022
DORA PSI
Paladino D, Dreier J
Passive containment cooling system (PCCS) response with Drywell Gas Recirculation System (DGRS) activated during a postulated Loss of Coolant Accident (LOCA)
Nuclear Engineering and Design. 2011; 241(9): 3925-3934. https://doi.org/10.1016/j.nucengdes.2011.07.016
DORA PSI
Pelloni S, Mikityuk K
A new cross-section generation model in the FAST code system and its application to gas- and sodium-cooled Generation IV fast reactors
Annals of Nuclear Energy. 2011; 38(1): 1-13. https://doi.org/10.1016/j.anucene.2010.08.009
DORA PSI
Perez M, Reventos F, Batet L, Guba A, Tóth I, Mieusset T, et al.
Uncertainty and sensitivity analysis of a LBLOCA in a PWR nuclear power plant: results of the phase V of the BEMUSE programme
Nuclear Engineering and Design. 2011; 241(10): 4206-4222. https://doi.org/10.1016/j.nucengdes.2011.08.019
DORA PSI
Petrov V, Manera A
Effect of pump-induced cold-leg swirls on the flow field in the RPV of the EPR^TM: CFD investigations and comparison with experimental results
Nuclear Engineering and Design. 2011; 241(5): 1478-1485. https://doi.org/10.1016/j.nucengdes.2011.02.027
DORA PSI
Pittarello R, Vasiliev A, Ferroukhi H, Chawla R
Refined Monte Carlo analysis of the H.B. Robinson-2 reactor pressure vessel dosimetry benchmark
Annals of Nuclear Energy. 2011; 38(9): 1842-1851. https://doi.org/10.1016/j.anucene.2011.05.017
DORA PSI
Puragliesi R, Dehbi A, Leriche E, Soldati A, Deville MO
DNS of buoyancy-driven flows and Lagrangian particle tracking in a square cavity at high Rayleigh numbers
International Journal of Heat and Fluid Flow. 2011; 32(5): 915-931. https://doi.org/10.1016/j.ijheatfluidflow.2011.06.007
DORA PSI
Ritterath M, Prasser H-M, Bouquet T, Paladino D, Mignot G
New gas concentration measurement system for the PANDA containment test facility
Nuclear Engineering and Design. 2011; 241(11): 4594-4603. https://doi.org/10.1016/j.nucengdes.2010.09.017
DORA PSI
Rätz D, Jordan KA, Murphy MF, Perret G, Chawla R
Comparison of measured and calculated reaction rate distributions in an scwr-like test lattice
Annals of Nuclear Energy. 2011; 38(4): 794-801. https://doi.org/10.1016/j.anucene.2010.11.021
DORA PSI
Rätz D, Jordan KA, Perret G, Chawla R
Experimental validation of control rod related perturbations of moderator regions in an SCWR-like fuel lattice
Annals of Nuclear Energy. 2011; 38(11): 2319-2332. https://doi.org/10.1016/j.anucene.2011.07.007
DORA PSI
Stainsby R, Peers K, Mitchell C, Poette C, Mikityuk K, Somers J
Gas cooled fast reactor research in Europe
Nuclear Engineering and Design. 2011; 241(9): 3481-3489. https://doi.org/10.1016/j.nucengdes.2011.08.005
DORA PSI
Stuckert J, Birchley J, Große M, Jaeckel B, Steinbrück M
Experimental and calculation results of the integral reflood test QUENCH-15 with ZIRLO^TMcladding tubes in comparison with results of previous QUENCH tests
Nuclear Engineering and Design. 2011; 241(8): 3224-3233. https://doi.org/10.1016/j.nucengdes.2011.05.004
DORA PSI
Sun K, Krepel J, Mikityuk K, Pelloni S, Chawla R
Void reactivity decomposition for the Sodium-cooled Fast Reactor in equilibrium fuel cycle
Annals of Nuclear Energy. 2011; 38(7): 1645-1657. https://doi.org/10.1016/j.anucene.2011.02.018
DORA PSI
Vasiliev A, Kolbe E, Ferroukhi H, Pittarello R
Comparison of neutron data libraries for the analysis of the "H. B. ROBINSON-2 Pressure Vessel Benchmark" with the MCNPX code
Journal of the Korean Physical Society. 2011; 59(23): 2047-2050. https://doi.org/10.3938/jkps.59.2047
DORA PSI
Vinai P, Macian-Juan R, Chawla R
Propagation of void fraction uncertainty measures in the RETRAN-3D simulation of the Peach Bottom turbine trip
Annals of Nuclear Energy. 2011; 38(2-3): 358-370. https://doi.org/10.1016/j.anucene.2010.10.007
DORA PSI
Yun Y, Oppeneer PM
First-principles design of next-generation nuclear fuels
MRS Bulletin. 2011; 36(3): 178-184. https://doi.org/10.1557/mrs.2011.34
DORA PSI
Zboray R, Kickhofel J, Damsohn M, Prasser H-M
Cold-neutron tomography of annular flow and functional spacer performance in a model of a boiling water reactor fuel rod bundle
Nuclear Engineering and Design. 2011; 241(8): 3201-3215. https://doi.org/10.1016/j.nucengdes.2011.06.029
DORA PSI
Zboray R, Prasser H-M
On the relevance of low side flows for thermal loads in T-junctions
Nuclear Engineering and Design. 2011; 241(8): 2881-2888. https://doi.org/10.1016/j.nucengdes.2011.05.002
DORA PSI
Zerkak O, Ferroukhi H
Vessel coolant mixing effects on a PWR Main Steam Line Break transient
Annals of Nuclear Energy. 2011; 38(1): 60-71. https://doi.org/10.1016/j.anucene.2010.08.016
DORA PSI
Andreani M, Paladino D, George T
Simulation of basic gas mixing tests with condensation in the PANDA facility using the GOTHIC code
Nuclear Engineering and Design. 2010; 240(6): 1528-1547. https://doi.org/10.1016/j.nucengdes.2010.02.021
DORA PSI
Andreani M, Paladino D
Simulation of gas mixing and transport in a multi-compartment geometry using the GOTHIC containment code and relatively coarse meshes
Nuclear Engineering and Design. 2010; 240(6): 1506-1527. https://doi.org/10.1016/j.nucengdes.2010.02.020
DORA PSI
Aounallah Y
Development of a wide-range pre-CHF convective boiling correlation
Journal of Nuclear Science and Technology. 2010; 47(4): 357-366. https://doi.org/10.3327/jnst.47.357
DORA PSI
Dehbi A
Validation against DNS statistics of the normalized Langevin model for particle transport in turbulent channel flows
Powder Technology. 2010; 200(1-2): 60-68. https://doi.org/10.1016/j.powtec.2010.02.009
DORA PSI
Epiney A, Mikityuk K, Chawla R
Heavy-gas injection in the Generation IV gas-cooled fast reactor for improved decay heat removal under depressurized conditions
Nuclear Engineering and Design. 2010; 240(10): 3115-3125. https://doi.org/10.1016/j.nucengdes.2010.05.030
DORA PSI
Epiney A, Mikityuk K, Chawla R
TRACE qualification via analysis of the EIR gas-loop experiments with smooth rods
Annals of Nuclear Energy. 2010; 37(6): 875-887. https://doi.org/10.1016/j.anucene.2010.01.020
DORA PSI
Freixa J, Manera A
Analysis of an RPV upper head SBLOCA at the ROSA facility using TRACE
Nuclear Engineering and Design. 2010; 240(7): 1779-1788. https://doi.org/10.1016/j.nucengdes.2010.02.007
DORA PSI
Herranz LE, Ball J, Auvinen A, Bottomley D, Dehbi A, Housiadas C, et al.
Progress in understanding key aerosol issues
Progress in Nuclear Energy. 2010; 52(1): 120-127. https://doi.org/10.1016/j.pnucene.2009.09.013
DORA PSI
Kolbe E, Vasiliev A, Ferroukhi H
The effect of modern thermal neutron scattering sublibraries on criticality safety evaluations of wet storage pools
Annals of Nuclear Energy. 2010; 37(3): 371-379. https://doi.org/10.1016/j.anucene.2009.12.003
DORA PSI
Kosa M, Tan J-C, Merrill CA, Krack M, Cheetham AK, Parrinello M
Probing the mechanical properties of hybrid inorganic-organic frameworks: a computational and experimental study
ChemPhysChem. 2010; 11(11): 2332-2336. https://doi.org/10.1002/cphc.201000362
DORA PSI
Krepel J, Pelloni S, Mikityuk K, Coddington P
GFR equilibrium cycle analysis with the EQL3D procedure
Nuclear Engineering and Design. 2010; 240(4): 905-917. https://doi.org/10.1016/j.nucengdes.2009.12.007
DORA PSI
Kröhnert H, Perret G, Murphy MF, Chawla R
Freshly induced short-lived gamma-ray activity as a measure of fission rates in lightly re-irradiated spent fuel
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2010; 624(1): 101-108. https://doi.org/10.1016/j.nima.2010.09.033
DORA PSI
Kuhn S, Braillard O, Ničeno B, Prasser H-M
Computational study of conjugate heat transfer in T-junctions
Nuclear Engineering and Design. 2010; 240(6): 1548-1557. https://doi.org/10.1016/j.nucengdes.2010.02.022
DORA PSI
Liao Y, Guentay S, Vierow K
Local nonsimilarity method for the two-phase boundary layer in mixed convection laminar film condensation
Heat and Mass Transfer. 2010; 46(4): 447-455. https://doi.org/10.1007/s00231-010-0588-4
DORA PSI
Lind T, Ammar Y, Dehbi A, Güntay S
De-agglomeration mechanisms of TiO₂ aerosol agglomerates in PWR steam generator tube rupture conditions
Nuclear Engineering and Design. 2010; 240(8): 2046-2053. https://doi.org/10.1016/j.nucengdes.2010.03.002
DORA PSI
Mikityuk K
Analytical model of the oxide layer build-up in complex lead-cooled systems
Nuclear Engineering and Design. 2010; 240(10): 3632-3637. https://doi.org/10.1016/j.nucengdes.2010.07.005
DORA PSI
Mikityuk K, Krepel J, Pelloni S, Chenu A, Petkevich P, Chawla R
FAST code system: review of recent developments and near-future plans
Journal of Engineering for Gas Turbines and Power. 2010; 132(10): 102915 (7 pp.). https://doi.org/10.1115/1.4000336
DORA PSI
Niceno B, Sato Y, Badillo A, Andreani M
Multi-scale modeling and analysis of convective boiling: towards the prediction of CHF in rod bundles
Nuclear Engineering and Technology. 2010; 42(6): 620-635.
DORA PSI
Paladino D, Zboray R, Andreani M, Dreier J
Flow transport and mixing induced by horizontal jets impinging on a vertical wall of the multi-compartment PANDA facility
Nuclear Engineering and Design. 2010; 240(8): 2054-2065. https://doi.org/10.1016/j.nucengdes.2010.03.036
DORA PSI
Paladino D, Zboray R, Auban O
The panda tests 9 and 9bis investigating gas mixing and stratification triggered by low momentum plumes
Nuclear Engineering and Design. 2010; 240(5): 1262-1270. https://doi.org/10.1016/j.nucengdes.2010.01.017
DORA PSI
Paladino D, Zboray R, Benz P, Andreani M
Three-gas mixture plume inducing mixing and stratification in a multi-compartment containment
Nuclear Engineering and Design. 2010; 240(2): 210-220. https://doi.org/10.1016/j.nucengdes.2008.07.014
DORA PSI
Revents F, Pérez M, Batet L, Pericas R, Toth I, Bazin P, et al.
Main Results of phase IV BEMUSE project: Simulation of LBLOCA in an NPP
Science and Technology of Nuclear Installations. 2010; 2010: 219294. https://doi.org/10.1155/2010/219294
DORA PSI
Rohde M, Marcel CP, Manera A, Van der Hagen THJJ, Shiralkar B
Investigating the ESBWR stability with experimental and numerical tools: a comparative study
Nuclear Engineering and Design. 2010; 240(2): 375-384. https://doi.org/10.1016/j.nucengdes.2008.01.016
DORA PSI
Stuckert J, Birchley J, Grosse M, Jaeckel B, Steinbrück M
Experimental and calculation results of the integral reflood test QUENCH-14 with M5^® cladding tubes
Annals of Nuclear Energy. 2010; 37(8): 1036-1047. https://doi.org/10.1016/j.anucene.2010.04.015
DORA PSI
Vasiliev A, Ferroukhi H, Kolbe E
Performance of a Monte-Carlo solution for the H.B. Robinson-2 Pressure Vessel Dosimetry Benchmark
Annals of Nuclear Energy. 2010; 37(10): 1404-1410. https://doi.org/10.1016/j.anucene.2010.05.019
DORA PSI
Walker C, Manera A, Niceno B, Simiano M, Prasser HM
Steady-state RANS-simulations of the mixing in a T-junction
Nuclear Engineering and Design. 2010; 240(9): 2107-2115. https://doi.org/10.1016/j.nucengdes.2010.05.056
DORA PSI
Zboray R, Paladino D
Experiments on basic thermalhydraulic phenomena relevant for LWR containments: gas mixing and transport induced by buoyant jets in a multi-compartment geometry
Nuclear Engineering and Design. 2010; 240(10): 3158-3169. https://doi.org/10.1016/j.nucengdes.2010.05.047
DORA PSI

Assessment Of GOTHIC And TRACE Codes Against Selected Panda Experiments On A Passive Containment Condenser
D. Papini, C. Adamsson, M. Andreani, H-M. Prasser
Nuclear Engineering and Design, Vol. 278, Pp. 542-557 (2014)

Post-Test Thermal-Hydraulic Analysis Of Two Intermediate LOCA Tests At The Rosa Facility Including Uncertainty Evaluation
J. Freixa, W-W. Kim, A. Manera
Nuclear Engineering And Design, Vol. 264, Pp 153-160 (2013)
http://dx.doi.org/10.1016/j.nucengdes.2013.02.023

Large Eddy Simulation Of The Differentially Heated Cubic Cavity Flow By The Spectral Element Method
C. Bosshard, A. Dehbi, E. Leriche, R. Puragliesi, A. Soldati
Computers And Fluids, Vol. 86, Pp. 210-227 (2013)

Simulation Of Halden IFA-650 Loss-Of-Coolant Accidents Tests With TRACE
Y. Aounallah
Kerntechnik, Vol 77, Pp 316-323 (2012)

Analysis Of The Isp-50 Direct Vessel Injection Sbloca In The ATLAS Facility Witth The RELAP5/MOD3.3 Code
M. Sharabi, J. Freixa
Nuclear Engineering And Technology, Vol. 44, Pp 709-718 (2012)

Analysis Of Void Fraction Distribution And Departure From Nucleate Boiling In Single Subchannel And Bundle Geometries Using Subchannel, System, And Computational Fluid Dynamics Codes
T-W. Kim, V. Petrov, A. Manera, S. Lo
Science And Technology of Nuclear Installations, Vol.2012, Article Id 746467 (2012)

Quantitative Evaluation Of Change In Core Damage Frequency By Postulated Power Uprate: Medium-Break Loss-Of-Coolant-Accidents
T-W. Kim, V.N. Dang, M.A. Zimmermann, A. Manera
Annals of Nuclear Energy, Vol. 47, September 2012, Pp. 69-80 (2012)

Remarks On Consistent Development Of Plant Nodalizations: An Example Of Application To The Rosa Integral Test Facility
J. Freixa, A. Manera
Science And Technology of Nuclear Installations, Vol. 2012, Article Id 158617 (2012)

Effect Of Pump-Induced Cold-Leg Swirls On The Flow Field In The RPV Of The EPR - CFD Investigations And Comparison With Experimental Results
V. Petrov, A. Manera
Nuclear Engineering And Design, Vol. 241, Issue 5, May 2011, Pp 1476-1485 (2011)

Analysis Of An Ads Spurious Opening Event At A BWR/6 By Means Of The TRACE Code
K. Nikitin, A. Manera
Nuclear Engineering And Design, Doi: 10.1016/J.Nucengdes2011.03.021 (2011)

Verification Of A TRACE EPR Model On The Basis Of A Scaling Calculation Of An SBLOCA Rosa Test
J. Freixa, A. Manera
Nuclear Engineering And Design, Volume 241, Issue 3, March 2011, P 888-896 (2011)

Uncertainty And Sensitivity Analysis Of A LBLOCA In A PWR Nuclear Power Plant: Results Of The Phase V Of The Bemuse Programme
M. Perez, F. Reventosa, L. Batet, A. Guba, I. TóTh, T. Mieusset, P. Bazin, A. De CréCy, S. Borisov, T. Skorek, H. Glaeser, J. Joucla, P. Probst, A. Ui, B.D. Chung, D.Y. Oh, R. Pernica, M. Kyncl, J. Macek, A. Manera, J. Freixa, A. Petruzzi, F. D’Auria, A. Del Nevo
Nuclear Engineering And Design, Vol. 241, Issue 10, Pp 4206-4222, October 2011

Modeling And Validation Of A Mechanistic Tool (Mefisto) For The Prediction Of Critical Power In BWR Fuel Assemblies
C. Adamsson, J-M. Le Corre
Nuclear Engineering And Design, Vol. 241, Issue 8, Pp 2843-2858, August 2011

First_principles Investigation Of Higher Oxides Of Uranium And Neptunium: U3o8 And Np20
Y. Yun, J. Rusz, M-T. Suzuki, P.M. Oppeneer
Physical Review, B 83, 075109, Doi: 10.1103/Phyrevb.83.075109(2011)

Improvements Of The One-Dimensional Dissolved Solute Convection Equation Using The Quickest-Ultimate Algorithm
D. Bertolotto, A. Manera, R. Macian-Juan, R. Chawla
Nuclear Engineering and Design,
http://dx.doi.org/10.1016/J.Nucengdes.2010.10.021 (2010)

Development Of A Wide-Range Pre-Chf Convective Boiling Correlation
Y. Aounallah
Journal of Nuclear Science And Technology, Vol. 47(4), Pp. 357-366, 2010

Analysis Of An Rpv Upper Head SBLOCA oca At The Rosa Facility Using TRACE
J. Freixa, A. Manera
Nuclear Engineering And Design, Available Online 30 March, 2010

First_principles Study Of Helium Behavior In Nuclear Fuel Materials
Y. Yun, O. Eriksson, P. M. Oppeneer
Chapter 7, Nova Science Publishers, Helium: Characteristics, Compounds And Applications, Isbn:978-1-61761-213-8 (2010)

Main Results Of Phase IV Bemuse Project. Simulation Of LBLCOA In A NPP
M. PéRez, F. ReventóS, L. Batet, R. Pericas, I. Toth, P. Bazin, CréCy. De, Germain. A, Borisov. P, Glaeser. S, Skorek. H, Joucla. T, Probst. J, Ui. P, Chung. A, Oh. B, Y. D, M. Kyncl, R. Pernica, A. Manera, F. D'Auria, A. Petruzzi, Nevo. Del,
Science And Technology of Nuclear Installations (Issn 1687-6075), Vol. 2010, Id 219294 (2010)

Investigating The ESBWR Stability With Experimental And Numerical Tools: A Comparative Study
M. Rohde, C. Marcel, Manera. P, Van. A, Hagen. Der, H. T, J. J, B. Shiralkar
Nuclear Engineering and Des. (Issn 0029-5493), 240(2), 375-384 (2010)

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2005 - 2009

Bertolotto D, Manera A, Frey S, Prasser H-M, Chawla R
Single-phase mixing studies by means of a directly coupled CFD/system-code tool
Annals of Nuclear Energy. 2009; 36(3): 310-316. https://doi.org/10.1016/j.anucene.2008.11.027
DORA PSI
Caravati S, Bernasconi M, Kühne TD, Krack M, Parrinello M
Unravelling the mechanism of pressure induced amorphization of phase change materials
Physical Review Letters. 2009; 102(20): 205502. https://doi.org/10.1103/PhysRevLett.102.205502
DORA PSI
Caruso S, Murphy MF, Jatuff F, Chawla R
Determination of within-rod caesium and europium isotopic distributions in high burnup fuel rods through computerised gamma-ray emission tomography
Nuclear Engineering and Design. 2009; 239(7): 1220-1228. https://doi.org/10.1016/j.nucengdes.2009.02.019
DORA PSI
Chawla R
Editorial
Annals of Nuclear Energy. 2009; 36(3): 255-257. https://doi.org/10.1016/j.anucene.2008.11.008
DORA PSI
Chenu A, Mikityuk K, Chawla R
TRACE simulation of sodium boiling in pin bundle experiments under loss-of-flow conditions
Nuclear Engineering and Design. 2009; 239(11): 2417-2429. https://doi.org/10.1016/j.nucengdes.2009.07.015
DORA PSI
Cucinotta CS, Miceli G, Raiteri P, Krack M, Kühne TD, Bernasconi M, et al.
Superionic Conduction in Substoichiometric LiAl Alloy: An Ab Initio Study
Physical Review Letters. 2009; 103(12): 125901. https://doi.org/10.1103/PhysRevLett.103.125901
DORA PSI
Dehbi A
A stochastic Langevin model of turbulent particle dispersion in the presence of thermophoresis
International Journal of Multiphase Flow. 2009; 35(3): 219-226. https://doi.org/10.1016/j.ijmultiphaseflow.2008.11.006
DORA PSI
Dhotre MT, Niceno B, Smith BL, Simiano M
Large-eddy simulation (LES) of the large scale bubble plume
Chemical Engineering Science. 2009; 64(11): 2692-2704. https://doi.org/10.1016/j.ces.2009.02.040
DORA PSI
Ferroukhi H, Zerkak O, Chawla R
Cross-section modelling effects on pressurised water reactor main steam line break analyses
Annals of Nuclear Energy. 2009; 36(8): 1184-1200. https://doi.org/10.1016/j.anucene.2009.04.006
DORA PSI
Ferroukhi H, Hollard JM, Zimmermann MA, Chawla R
Estimation of the fast neutron fluence at control rod tips using a 3-D diffusion/2-D transport multi-step calculation scheme
Annals of Nuclear Energy. 2009; 36(3): 286-291. https://doi.org/10.1016/j.anucene.2008.12.010
DORA PSI
Ferroukhi H, Zimmermann MA
Study of the PWR REA pulse width for realistic UO₂ and MOX core designs using 3D kinetics methods
Annals of Nuclear Energy. 2009; 36(8): 1170-1183. https://doi.org/10.1016/j.anucene.2009.04.007
DORA PSI
Jatuff F, Perret G, Murphy MF, Giust F, Chawla R
Void reactivity coefficient benchmark results for a 10 × 10 BWR assembly in the full 0-100% void fraction range
Annals of Nuclear Energy. 2009; 36(6): 853-858. https://doi.org/10.1016/j.anucene.2009.02.013
DORA PSI
Krack M
First-principles study of crystalline and amorphous Ge(2)Sb(2)Te(5) and the effects of stoichiometric defects
Journal of Physics: Condensed Matter. 2009; 21(25): 255501. https://doi.org/10.1088/0953-8984/21/25/255501
DORA PSI
Krepel J, Pelloni S, Mikityuk K, Coddington P
EQL3D: ERANOS based equilibrium fuel cycle procedure for fast reactors
Annals of Nuclear Energy. 2009; 36(5): 550-561. https://doi.org/10.1016/j.anucene.2009.01.008
DORA PSI
Kühne TD, Krack M, Parrinello M
Static and dynamical properties of liquid water from first principles by a novel car-parrinello-like approach http://pubs.acs.org
Journal of Chemical Theory and Computation. 2009; 5(2): 235-241. https://doi.org/10.1021/ct800417q
DORA PSI
Liao Y, Guentay S, Suckow D, Dehbi A
Reflux condensation of flowing vapor and non-condensable gases counter-current to laminar liquid film in a vertical tube
Nuclear Engineering and Design. 2009; 239(11): 2409-2416. https://doi.org/10.1016/j.nucengdes.2009.07.006
DORA PSI
Liao Y, Vierow K, Dehbi A, Guentay S
Transition from natural to mixed convection for steam-gas flow condensing along a vertical plate
International Journal of Heat and Mass Transfer. 2009; 52(1-2): 366-375. https://doi.org/10.1016/j.ijheatmasstransfer.2008.06.008
DORA PSI
Liu L-M, Krack M, Michaelides A
Interfacial water: A first principles molecular dynamics study of a nanoscale water film on salt
Journal of Chemical Physics. 2009; 130(23): 234702. https://doi.org/10.1063/1.3152845
DORA PSI
Manera A, Ozar B, Paranjape S, Ishii M, Prasser HM
Comparison between wire-mesh sensors and conductive needle-probes for measurements of two-phase flow parameters
Nuclear Engineering and Design. 2009; 239(9): 1718-1724. https://doi.org/10.1016/j.nucengdes.2008.06.015
DORA PSI
Mikityuk K
Heat transfer to liquid metal: Review of data and correlations for tube bundles
Nuclear Engineering and Design. 2009; 239(4): 680-687. https://doi.org/10.1016/j.nucengdes.2008.12.014
DORA PSI
Perret G, Murphy MF, Jatuff F, Sublet JC, Bouland O, Chawla R
Impact of new gadolinium cross sections on reaction rate distributions in 10×10 BWR assemblies
Nuclear Science and Engineering. 2009; 163(1): 17-25. https://doi.org/10.13182/NSE08-55
DORA PSI
Petkevich P, Mikityuk K, Coddington P, Chawla R
Development and benchmarking of a mechanical model for GFR plate-type fuel
Annals of Nuclear Energy. 2009; 36(8): 1262-1269. https://doi.org/10.1016/j.anucene.2009.01.015
DORA PSI
Plaschy M, Murphy M, Jatuff F, LÜthi A, Grimm P, Jacot-Guillarmod R, et al.
Experimental Validation of Reaction Rate Distributions for a SVEA-96+ BWR Assembly with Hafnium Control Blades
Journal of Nuclear Science and Technology. 2009; 46(9): 933-943. https://doi.org/10.1080/18811248.2009.9711602
DORA PSI
Plaschy M, Murphy M, Jatuff F, Perret G, Seiler R, Chawla R
Validation of Monte Carlo predictions of LWR-PROTEUS safety parameters using an improved whole-reactor model
Annals of Nuclear Energy. 2009; 36(10): 1536-1543. https://doi.org/10.1016/j.anucene.2009.07.012
DORA PSI
Romano A, Shuffler CA, Garkisch HD, Olander DR, Todreas NE
Fuel performance analysis for PWR cores
Nuclear Engineering and Design. 2009; 239(8): 1481-1488. https://doi.org/10.1016/j.nucengdes.2008.11.022
DORA PSI
Stainsby R, Peers K, Mitchell C, Poette C, Mikityuk K, Somers J
Gas cooled fast reactor research and development in the European Union
Science and Technology of Nuclear Installations. 2009; 2009: 238624. https://doi.org/10.1155/2009/238624
DORA PSI
Walker C, Simiano M, Zboray R, Prasser HM
Investigations on mixing phenomena in single-phase flow in a T-junction geometry
Nuclear Engineering and Design. 2009; 239(1): 116-126. https://doi.org/10.1016/j.nucengdes.2008.09.003
DORA PSI
Andreani M, Haller K, Heitsch M, Hemström B, Karppinen I, Macek J, et al.
A benchmark exercise on the use of CFD codes for containment issues using best practice guidelines: a computational challenge
Nuclear Engineering and Design. 2008; 238(3): 502-513. https://doi.org/10.1016/j.nucengdes.2007.01.021
DORA PSI
Aounallah Y
A separate-effect-based new appraisal of convective boiling and its suppression
Journal of Nuclear Science and Technology. 2008; 45(2): 149-159. https://doi.org/10.3327/jnst.45.149
DORA PSI
Barten W, Jasiulevicius A, Manera A, Macian-Juan R, Zerkak O
Analysis of the capability of system codes to model cavitation water hammers: Simulation of UMSICHT water hammer experiments with TRACE and RELAP5
Nuclear Engineering and Design. 2008; 238(4): 1129-1145. https://doi.org/10.1016/j.nucengdes.2007.10.004
DORA PSI
Barten W, Manera A, Macian-Juan R
One- and two-dimensional standing pressure waves and one-dimensional travelling pulses using the US-NRC nuclear systems analysis code TRACE
Nuclear Engineering and Design. 2008; 238(10): 2568-2582. https://doi.org/10.1016/j.nucengdes.2008.05.004
DORA PSI
Blair P, Khvostov G, Romano A, Hellwig C, Chawla R
Interpretation of high-burnup fuel annealing tests
Journal of Nuclear Science and Technology. 2008; 45(7): 639-646. https://doi.org/10.1080/18811248.2008.9711463
DORA PSI
Bubelis E, Castelliti D, Coddington P, Dor I, Fouillet C, de Geus E, et al.
A GFR benchmark: Comparison of transient analysis codes based on the ETDR concept
Progress in Nuclear Energy. 2008; 50(1): 37-51. https://doi.org/10.1016/j.pnucene.2007.11.090
DORA PSI
Bubelis E, Coddington P, Mikityuk K
Verification of the TRACE code against the MEGAPIE transient data
Annals of Nuclear Energy. 2008; 35(7): 1284-1295. https://doi.org/10.1016/j.anucene.2007.12.006
DORA PSI
Caruso S, Günther-Leopold I, Murphy MF, Jatuff F, Chawla R
Comparison of optimised germanium gamma spectrometry and multicollector inductively coupled plasma mass spectrometry for the determination of ¹³⁴Cs, ¹³⁷Cs and ¹⁵⁴Eu single ratios in highly burnt UO₂
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2008; 589(3): 425-435. https://doi.org/10.1016/j.nima.2008.03.005
DORA PSI
Caruso S, Murphy MF, Jatuff F, Chawla R
Nondestructive determination of fresh and spent nuclear fuel rod density distributions through computerised gamma-ray transmission tomography
Journal of Nuclear Science and Technology. 2008; 45(8): 828-835. https://doi.org/10.3327/jnst.45.828
DORA PSI
Chawla R, Jatuff F, Tani F
Diagnostic analysis of pin-removal reactivity worth experiments in a SVEA-96+ test lattice
Annals of Nuclear Energy. 2008; 35(3): 495-502. https://doi.org/10.1016/j.anucene.2007.06.027
DORA PSI
Cometto M, Wydler P, Chawla R
Management of actinide waste inventories in nuclear phase-out scenarios
Annals of Nuclear Energy. 2008; 35(8): 1447-1460. https://doi.org/10.1016/j.anucene.2008.01.016
DORA PSI
Dehbi A
A CFD model for particle dispersion in turbulent boundary layer flows
Nuclear Engineering and Design. 2008; 238(3): 707-715. https://doi.org/10.1016/j.nucengdes.2007.02.055
DORA PSI
Dehbi A
Turbulent particle dispersion in arbitrary wall-bounded geometries: A coupled CFD-Langevin-equation based approach
International Journal of Multiphase Flow. 2008; 34(9): 819-828. https://doi.org/10.1016/j.ijmultiphaseflow.2008.03.001
DORA PSI
Dhotre MT, Niceno B, Smith BL
Large eddy simulation of a bubble column using dynamic sub-grid scale model
Chemical Engineering Journal. 2008; 136(2-3): 337-348. https://doi.org/10.1016/j.cej.2007.04.016
DORA PSI
Fazio C, Gröschel F, Wagner W, Thomsen K, Smith BL, Stieglitz R, et al.
The MEGAPIE-TEST project: Supporting research and lessons learned in first-of-a-kind spallation target technology
Nuclear Engineering and Design. 2008; 238(6): 1471-1495. https://doi.org/10.1016/j.nucengdes.2007.11.006
DORA PSI
Girardin G, Rimpault G, Morin F, Bosq JC, Coddington P, Mikityuk K, et al.
Development and characterization of the control assembly system for the large 2400 MWth Generation IV gas-cooled fast reactor
Annals of Nuclear Energy. 2008; 35(12): 2206-2218. https://doi.org/10.1016/j.anucene.2008.09.008
DORA PSI
Hawlitzky M, Horbach J, Ispas S, Krack M, Binder K
Comparative classical and 'ab initio' molecular dynamics study of molten and glassy germanium dioxide
Journal of Physics: Condensed Matter. 2008; 20(28): 285106. https://doi.org/10.1088/0953-8984/20/28/285106
DORA PSI
Kolbe E, Vasiliev A, Ferroukhi H, Zimmermann MA
Consistent evaluation of modern nuclear data libraries for criticality safety analyses of thermal compound low-enriched-uranium systems
Annals of Nuclear Energy. 2008; 35(10): 1831-1841. https://doi.org/10.1016/j.anucene.2008.04.009
DORA PSI
Kosa M, Krack M, Cheetham AK, Parrinello M
Modeling the hydrogen storage materials with exposed M2+ coordination sites
Journal of Physical Chemistry C. 2008; 112(42): 16171-16173. https://doi.org/10.1021/jp806394g
DORA PSI
Krepel J, Rohde U, Grundmann U, Weiss F-P
Dynamics of molten salt reactors
Nuclear Technology. 2008; 164(1): 44. https://doi.org/10.13182/NT08-A4006
DORA PSI
Liu L, Krack M, Michaelides A
Density oscillations in a nanoscale water film on salt: Insight from ab initio molecular dynamics
Journal of the American Chemical Society. 2008; 130(27): 8572-8573. https://doi.org/10.1021/ja8014296
DORA PSI
Mikityuk K, Coddington P, Gröschel F
Analysis of radioactivity releases in the MEGAPIE reference accident
Nuclear Engineering and Design. 2008; 238(7): 1838-1844. https://doi.org/10.1016/j.nucengdes.2007.12.004
DORA PSI
Murphy MF, Jatuff F, Perret G, Plaschy M, Bergmann U, Chawla R
Comparison of 3D reaction rate distributions measured in an Optima2 BWR assembly with MCNPX predictions
Annals of Nuclear Energy. 2008; 35(11): 2042-2050. https://doi.org/10.1016/j.anucene.2008.06.001
DORA PSI
Ničeno B, Dhotre MT, Deen NG
One-equation sub-grid scale (SGS) modelling for Euler-Euler large eddy simulation (EELES) of dispersed bubbly flow
Chemical Engineering Science. 2008; 63(15): 3923-3931. https://doi.org/10.1016/j.ces.2008.04.050
DORA PSI
Perret G, Plaschy M, Murphy MF, Jatuff F, Chawla R
Characterisation of radial reaction rate distributions across the 92-pin section of a SVEA-96 Optima2 assembly
Annals of Nuclear Energy. 2008; 35(3): 478-484. https://doi.org/10.1016/j.anucene.2007.06.025
DORA PSI
Tereshatov EE, Bruchertseifer H, Bozhikov GA, Aksenov NV, Starodub GY, Vostokin GK, et al.
Cation-exchange separation of group V elements: model experiments on isolation and chemical identification of Db
Radiochemistry. 2008; 50(3): 290-293. https://doi.org/10.1134/S1066362208030132
DORA PSI
Vasiliev A, Ferroukhi H, Zimmermann MA, Chawla R
On the effects of oxygen cross-sections in the fast neutron fluence analysis for a reactor pressure vessel scraping test
Annals of Nuclear Energy. 2008; 35(4): 565-569. https://doi.org/10.1016/j.anucene.2007.08.018
DORA PSI
Vasiliev A, Kolbe E, Ferroukhi H, Zimmermann MA, Chawla R
On the performance of ENDF/B-VII.0 data for fast neutron fluence calculations
Annals of Nuclear Energy. 2008; 35(12): 2432-2435. https://doi.org/10.1016/j.anucene.2008.07.009
DORA PSI
Vasiliev A, Kolbe E, Zimmermann MA
Towards the development of upper subcriticality limits on the basis of benchmark criticality calculations
Annals of Nuclear Energy. 2008; 35(9): 1764-1773. https://doi.org/10.1016/j.anucene.2008.01.017
DORA PSI
Yadigaroglu G, Simiano M, Milenkovic R, Kubasch J, Milelli M, Zboray R, et al.
CFD4NRS with a focus on experimental and CMFD investigations of bubbly flows
Nuclear Engineering and Design. 2008; 238(3): 771-785. https://doi.org/10.1016/j.nucengdes.2007.02.047
DORA PSI
Atchison F, Bryś T, Daum M, Fierlinger P, Foelske A, Gupta M, et al.
Structural characterization of diamond-like carbon films for ultracold neutron applications
Diamond and Related Materials. 2007; 16(2): 334-341. https://doi.org/10.1016/j.diamond.2006.06.008
DORA PSI
Auban O, Zboray R, Paladino D
Investigation of large-scale gas mixing and stratification phenomena related to LWR containment studies in the PANDA facility
Nuclear Engineering and Design. 2007; 237(4): 409-419. https://doi.org/10.1016/j.nucengdes.2006.07.011
DORA PSI
Bergmann UC, Grimm P, Jatuff F, Murphy MF, Chawla R
Investigations of ²³⁸U captures to total fissions in a Westinghouse SVEA-96+ assembly
Nuclear Science and Engineering. 2007; 156(1): 86-95. https://doi.org/10.13182/NSE07-A2687
DORA PSI
Caravati S, Bernasconi M, Kühne TD, Krack M, Parrinello M
Coexistence of tetrahedral- and octahedral-like sites in amorphous phase change materials
Applied Physics Letters. 2007; 91(17): 171906. https://doi.org/10.1063/1.2801626
DORA PSI
Caruso S, Murphy M, Jatuff F, Chawla R
Validation of of ¹³⁴Cs, ¹³⁷Cs and ¹⁵⁴Eu single ratios as burnup monitors for ultra-high burnup UO₂ fuel
Annals of Nuclear Energy. 2007; 34(1-2): 28-35. https://doi.org/10.1016/j.anucene.2006.11.009
DORA PSI
Dhotre MT, Smith BL, Niceno B
CFD simulation of bubbly flows: Random dispersion model
Chemical Engineering Science. 2007; 62(24): 7140-7150. https://doi.org/10.1016/j.ces.2007.08.016
DORA PSI
Dokhane A, Hennig D, Rizwan-uddin, Chawla R
BWR stability and bifurcation analysis using reduced order models and system codes: identification of a subcritical Hopf bifurcation using RAMONA
Annals of Nuclear Energy. 2007; 34(10): 792-802. https://doi.org/10.1016/j.anucene.2007.04.003
DORA PSI
Dokhane A, Hennig D, Rizwan-uddin, Chawla R
Interpretation of in-phase and out-of-phase BWR oscillations using an extended reduced order model and semi-analytical bifurcation analysis
Annals of Nuclear Energy. 2007; 34(4): 271-287. https://doi.org/10.1016/j.anucene.2006.12.005
DORA PSI
Guentay S, Cripps R, Jaeckel B, Bruchertseifer H
Radiochemical studies of the retention of volatile iodine in aqueous solutions
Journal of Radioanalytical and Nuclear Chemistry. 2007; 273(3): 557-561. https://doi.org/10.1007/s10967-007-0909-3
DORA PSI
Macian R, Zimmermann MA, Chawla R
Statistical uncertainty analysis applied to fuel depletion calculations
Journal of Nuclear Science and Technology. 2007; 44(6): 875-885. https://doi.org/10.3327/jnst.44.875
DORA PSI
Macku K, Jatuff F, Murphy M, Plaschy M, Grimm P, Joneja OP, et al.
Radial and azimuthal ²³⁵U fission and ²³⁸U capture distributions in BWR UO₂ pins: CASMO-4 and MCNP4C versus activation foil measurements
Nuclear Science and Engineering. 2007; 155(1): 96-101. https://doi.org/10.13182/NSE07-A2647
DORA PSI
Mikityuk K, Coddington P, Pelloni S, Bubelis E, Chawla R
Comparative transient analysis of critical and subcritical 80-MW Pb-Bi eutectic-cooled reactor systems
Nuclear Technology. 2007; 157(1): 18-36. https://doi.org/10.13182/NT07-A3799
DORA PSI
Petkevich P, Mikityuk K, Coddington P, Chawla R
Development and benchmarking of a 2D transient thermal model for GFR plate-type fuel
Annals of Nuclear Energy. 2007; 34(9): 707-718. https://doi.org/10.1016/j.anucene.2007.03.009
DORA PSI
Romano A, Horvath MI, Restani R
Evolution of porosity in the high-burnup fuel structure
Journal of Nuclear Materials. 2007; 361(1): 62-68. https://doi.org/10.1016/j.jnucmat.2006.09.016
DORA PSI
Smith BL, Leung W, Zucchini A
Coupled fluid/structure analyses of the MEGAPIE spallation source target during transients
Nuclear Engineering and Design. 2007; 237(15-17 SPEC. ISS.): 1656-1667. https://doi.org/10.1016/j.nucengdes.2007.02.020
DORA PSI
Vasiliev A, Ferroukhi H, Zimmermann MA, Chawla R
Development of a CASMO-4/SIMULATE-3/MCNPX calculation scheme for PWR fast neutron fluence analysis and validation against RPV scraping test data
Annals of Nuclear Energy. 2007; 34(8): 615-627. https://doi.org/10.1016/j.anucene.2007.02.020
DORA PSI
Vinai P, Macian-Juan R, Chawla R
A statistical methodology for quantification of uncertainty in best estimate code physical models
Annals of Nuclear Energy. 2007; 34(8): 628-640. https://doi.org/10.1016/j.anucene.2007.03.003
DORA PSI
Zerkak O, Coddington P, Eitschberger H
Analysis of the Leibstadt power plant condensate and feedwater systems during selected operational transients
Nuclear Engineering and Design. 2007; 237(11): 1195-1208. https://doi.org/10.1016/j.nucengdes.2007.01.011
DORA PSI
Barten W, Coddington P, Ferroukhi H
RETRAN-3D analysis of the base case and the four extreme cases of the OECD/NRC Peach Bottom 2 Turbine Trip benchmark
Annals of Nuclear Energy. 2006; 33(2): 99-118. https://doi.org/10.1016/j.anucene.2005.09.011
DORA PSI
Bergmann UC, Chawla R, Jatuff F, Murphy MF
Optimised non-invasive method to determine ²³⁸U-captures-to-total-fissions in reactor fuel
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2006; 556(1): 331-338. https://doi.org/10.1016/j.nima.2005.08.110
DORA PSI
Blair P, Romano A, Hellwig C, Chawla R
Calculations on fission gas behaviour in the high burnup structure
Journal of Nuclear Materials. 2006; 350(3): 232-239. https://doi.org/10.1016/j.jnucmat.2006.01.006
DORA PSI
Dokhane A, Ferroukhi H, Zimmermann MA, Aguirre C
Spatial and model-order based reactor signal analysis methodology for BWR core stability evaluation
Annals of Nuclear Energy. 2006; 33(16): 1329-1338. https://doi.org/10.1016/j.anucene.2006.08.010
DORA PSI
Grimm P, Jatuff F, Murphy M, Seiler R, Williams T, Jacot-Guillarmod R, et al.
Experimental validation of channel bowing effects on pin power distributions in a Westinghouse SVEA-96+ assembly
Journal of Nuclear Science and Technology. 2006; 43(3): 223-230. https://doi.org/10.3327/jnst.43.223
DORA PSI
Hertzsch T, Gervais C, Hulliger J, Jaeckel B, Guentay S, Bruchertseifer H, et al.
Open‐pore organic material for retaining radioactive I₂ and CH₃I
Advanced Functional Materials. 2006; 16(2): 268-272. https://doi.org/10.1002/adfm.200500245
DORA PSI
Jatuff F, Giust F, Krouthén J, Helmersson S, Chawla R
Effects of void uncertainties on the void reactivity coefficient and pin power distributions for a 10 × 10 BWR assembly
Annals of Nuclear Energy. 2006; 33(2): 119-125. https://doi.org/10.1016/j.anucene.2005.09.007
DORA PSI
Jatuff F, Macku K, Chawla R
On the accuracy of reactor physics calculations for square HPLWR fuel assemblies
Annals of Nuclear Energy. 2006; 33(2): 198-207. https://doi.org/10.1016/j.anucene.2005.09.006
DORA PSI
Kapulla R, Najera SB
Operation conditions of a phase Doppler anemometer: Droplet size measurements with laser beam power, photomultiplier voltage, signal gain and signal-to-noise ratio as parameters
Measurement Science and Technology. 2006; 17(1): 221-227. https://doi.org/10.1088/0957-0233/17/1/034
DORA PSI
Kuijper JC, Raepsaet X, de Haas JBM, von Lensa W, Ohlig U, Ruetten H-J, et al.
HTGR reactor physics and fuel cycle studies
Nuclear Engineering and Design. 2006; 236(5-6): 615-634. https://doi.org/10.1016/j.nucengdes.2005.10.021
DORA PSI
Lucas D, Krepper E, Prasser H-M, Manera A
Investigations on the stability of the flow characteristics in a bubble column
Chemical Engineering and Technology. 2006; 29(9): 1066-1072. https://doi.org/10.1002/ceat.200600150
DORA PSI
Ma W, Bubelis E, Karbojian A, Sehgal BR, Coddington P
Transient experiments from the thermal-hydraulic ADS lead bismuth loop (TALL) and comparative TRAC/AAA analysis
Nuclear Engineering and Design. 2006; 236(13): 1422-1444. https://doi.org/10.1016/j.nucengdes.2006.01.006
DORA PSI
Macku K, Jatuff F, Murphy MF, Joneja OP, Bischofberger R, Chawla R
Advanced foil activation techniques for the measurement of within-pin distributions of the ⁶³Cu(n,γ)⁶⁴Cu reaction rate in nuclear fuel
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2006; 562(1): 393-400. https://doi.org/10.1016/j.nima.2006.03.004
DORA PSI
Mikityuk K, Coddington P, Bubelis E, Chawla R
Comparison of the transient behaviour of LBE-and gas-cooled experimental accelerator-driven systems
Nuclear Engineering and Design. 2006; 236(23): 2452-2473. https://doi.org/10.1016/j.nucengdes.2006.03.012
DORA PSI
Murphy MF, Jatuff F, Grimm P, Seiler R, Brogli R, Meier G, et al.
Reactivity and neutron emission measurements of highly burnt PWR fuel rod samples
Annals of Nuclear Energy. 2006; 33(9): 760-765. https://doi.org/10.1016/j.anucene.2006.04.003
DORA PSI
Paratte JM, Früh R, Kasemeyer U, Kalugin MA, Timm W, Chawla R
A benchmark on the calculation of kinetic parameters based on reactivity effect experiments in the CROCUS reactor
Annals of Nuclear Energy. 2006; 33(8): 739-748. https://doi.org/10.1016/j.anucene.2005.09.012
DORA PSI
Pelloni S, Bubelis E, Mikityuk K, Coddington P
Calculations of reactivity-initiated transients in gas-cooled fast reactors using the code system fast
Annals of Nuclear Energy. 2006; 33(6): 499-509. https://doi.org/10.1016/j.anucene.2006.01.002
DORA PSI
Pelloni S, Coddington P
On using alternative perturbation theory methodologies in the evaluation of reactivity effects in ADS cores
Annals of Nuclear Energy. 2006; 33(17-18): 1360-1367. https://doi.org/10.1016/j.anucene.2006.10.001
DORA PSI
Plaschy M, Jatuff F, Grimm P, Tani F, Jacot-Guillarmod R, Giust F, et al.
Comparisons of deterministic neutronic calculations with Monte Carlo results for an advanced BWR fuel assembly with hafnium control blades
Journal of Nuclear Science and Technology. 2006; 43(11): 1298-1310. https://doi.org/10.3327/jnst.43.1298
DORA PSI
Romano A, Li J, Yip S
Atomistic simulation of rapid compression of fractured silicon carbide
Journal of Nuclear Materials. 2006; 352(1-3): 22-28. https://doi.org/10.1016/j.jnucmat.2006.02.038
DORA PSI
Romano A, Wallin H, Zimmermann MA, Chawla R
Modelling the CABRI high-burnup RIA test CIP0-1 using an extended version of the FALCON code
Nuclear Engineering and Design. 2006; 236(3): 284-294. https://doi.org/10.1016/j.nucengdes.2005.08.007
DORA PSI
Simiano M, Zboray R, de Cachard F, Lakehal D, Yadigaroglu G
Comprehensive experimental investigation of the hydrodynamics of large-scale, 3D, oscillating bubble plumes
International Journal of Multiphase Flow. 2006; 32(10-11): 1160-1181. https://doi.org/10.1016/j.ijmultiphaseflow.2006.05.014
DORA PSI
Tani F, Jatuff F, Chawla R
Study of spectral heterogeneities for the interpretation of calculational trends in predicting pin power distributions in a SVEA-96+ BWR assembly
Annals of Nuclear Energy. 2006; 33(6): 490-498. https://doi.org/10.1016/j.anucene.2006.02.005
DORA PSI
Wenger HU, Al Mazouzi A, Atchison F, Burghartz M, Chawla R, Günther-Leopold I, et al.
Isobaric production cross sections from 0.6 GeV proton irradiation of neptunium and thorium using mass spectrometry
Nuclear Physics A. 2006; 764: 1-14. https://doi.org/10.1016/j.nuclphysa.2005.08.023
DORA PSI
Zilio VO, Joneja OP, Popowski Y, Rosenfeld A, Chawla R
Absolute depth-dose-rate measurements for an ¹⁹²Ir HDR brachytherapy source in water using MOSFET detectors
Medical Physics. 2006; 33(6): 1532-1539. https://doi.org/10.1118/1.2198168
DORA PSI

Single-Phase Mixing Studies By Means Of A Directly Coupled CFD/System-Code Tool
D. Bertolloto, A. Manera, S. Frey, H-M. Prasser, R. Chawla
Annals of Nuclear Energy, Volume 36, Issue 3, Pp 310-316 , April 2009

Advanced Microchannel Heat Exchanger With S-Shaped Fins
N. Tsuzuki, Y. Kato, K. Nikitin, T. Ishizuka
Journal of Nuclear Science And Technology, 46(5), 403-412 (2009)

Comparison Between Wire-Mesh Sensors And Conductive Needle-Probes For Measurements Of Two-Phase Flow Parameters
A. Manera, B. Ozar, S. Paranjape, M. Ishii, H. Prasser,
Nuclear Engineering and Des. (Issn 0029-5493), 239(9), 1718-1724 (2009)

Sbloca With Boron Dilution In Pressurized Water Reactors. Impact On Operation And Safety
J. Freixa, F. ReventóS, C. Pretel, L. Batet, I. Sol
Nuclear Engineering and Des. (Issn 0029-5493), 239(4), 749-760 (2009)

A Separate-Effect-Based New Appraisal Of Convective Boiling And Its Suppression
Y. Aounallah
Journal of Nuclear Sci. And Techn. (Issn 0022-3131), 45(2), 149-159 (2008)

One- And Two-Dimensional Standing Pressure Waves And One-Dimensional Travelling Pulses Using The US-NRC Nuclear Systems Analysis Code TRACE
W. Barten, A. Manera A., R. Macian-Juan
Nuclear Engineering and Des. (Issn 0029-5493), 238, 2568-2582 (2008)

Analysis Of The Capability Of System Codes To Model Cavitation Water Hammers: Simulation Of Umsicht Water Hammer Experiments With TRACE And RELAP5
W. Barten, A. Jasiulevicius, A. Manera, R. Macian-Juan, O. Zerkak
Nuclear Engineering and Des. (Issn 0029-5493), 238, 1129-1145 (2008)

A Generalized Mean Temperature Difference Method For Thermal Design Of Heat Exchangers
M. Utamura, K. Nikitin, Y. Kato
Ijnest, 4(1), (2008)

Steam Condensing Liquid CO2 Boiling Heat Transfer In A Steam Condenser For A New Heat Recovery System
K. Nikitin, Y. Kato, T. Ishizuka
International Journal of Heat And Mass Transfer, 51(17/18), 4544-4550 (2008)

Uncertainty And Sensitivity Analysis Of The Loft L2-5 Test: Results Of The Bemuse Programme
De CréCy A., Bazin P., Glaeser H., Skorek T., Joucla J., Probst P., Fujioka K., Chung B.D., Oh D.Y., Kyncl M., Pernica R., Macek J., Meca R., Macian R., D’Auria F. Petruzzi A. Bater L., Perez M., Reventos F.
Nuclear Engineering and Des. (Issn 0029-5493), 238, 3561-3578 (2008)

X-Ray Absorption Spectra Of Hexagonal Ice And Liquid Water By All-Electron Gaussian And Augmented Plane Wave Calculations
M. Iannuzzi-Mauri
J. Chem. Phys. (Issn 0021-9606), 128, 204506-204506-12 (2008)

First-Principles Molecular Dynamics Study Of The Heterogeneous Reduction Of NO2 On Soot Surfaces
Rodriguez-Fortea A., Iannuzzi Mauri M.
J. Phys. Chem C (Issn 1932-7447), 112, 19642-19648 (2008)

Modeling Bulk And Surface Pt Using The “Gaussian And Plane Wave” Density Functional Theory Formalism: Validation And Comparison To K-Point Plane Wave Calculations
G. Santarossa, A. Vargas, Mauri. Iannuzzi, Pignedoli. M, A. C, D. Passerone, A. Baiker
J. Chem. Phys. (Issn 0021-9606), 129, 234703-234703-12 (2008)

Chiral Recognition On Catalytic Surfaces: Theoretical Insight In A Biomimetic Heterogeneous Catalytic System
A. Vargas, G. Santarossa, Mauri. Iannuzzi, Baiker. M,
J. Phys. Chem C (Issn 1932-7447), 112, 10200-10208 (2008)

A Statistical Methodology For Quantification Of Uncertainty In Best Estimate Code Physical Models
P. Vinai, R. Macian-Juan, R. Chawla
Annals of Nuclear Energy, 34 (8), 628-640 (2007)

Analysis Of The Leibstadt Power Plant Condensate And Feedwater Systems During Selected Operational Transients
O. Zerkak, P. Coddington
Nuclear Science And Engineering, 237(11), 1195-1208 (2007)

Experimental Investigation On Bublbe Turbulent Diffusion In A Vertical Large-Diameter Pipe By Wire-Mesh Sensors And Correlation Techniques
A. Manera, H-M. Prasser, D. Lucas
Nuclear Technology, 158(2), 291-303 (2007)

Investigations On The Stability Of The Flow Characteristics In A Bubble Column
D. Lucas, E. Krepper, H. Prasser, Manera. M,
Chem. Engineering and Technol. (Issn 1521-4125), 9, 1066-1072 (2006)

Implications Of Alternative Strategies For Transitions To Sustainable Fuel Cycles
A. Romano, T. Boscher, P. Hejzlar, M. Kazimi, N. Todreas
Nuclear Sci. Engineering and (Issn 0029-5639), 154, 1-27 (2006)

Semi-Analytical Bifurcation Analysis Of Two-Phase Flow In A Heated Channel
A. Dokhane, D. Hennig, R. Chawla, Rizwan-Uddin
Int. J. Bifurcation Chaos (Issn 0218-1274), 15, 2395-2409 (2005)

Review Of The Licensing Basis For Ria And Loca Transients In Light Of New Evidence On High Burnup Fuel Behavior
M. Zimmermann, Bart. A,
Chimia (Issn 0009-4293), 59, 950-956 (2005)

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2001 - 2004

Void Fraction And Critical Power Assessment Of Coretran-01/Vipre-02
Y. Aounallah
Nuclear Technol. (Issn 0029-5450), 145, 163-176 (2004)

Peach Bottom BWR Turbine Trip Benchmark Analyses With Retran-3d And Coretran
W. Barten, H. Ferroukhi, P. Coddington
Nuclear Sci. Engineering and (Issn 0029-5639), 146, 306-324 (2004)

The Analysis Of Pwr And BWR Reactivity Transients With Coretran And Retran-3d
H. Ferroukhi, P. Coddington
Nuclear Technology, 142, 19-34 (2003)

Comparison Of Various Partial Light Water Reactor Core Loadings With Inert Matrix And Mixed-Oxide Fuel
U. Kasemeyer, Ch. Hellwig, J. Lebenhaft, R. Chawla
Journal of Nuclear Materials, 319, 142-153 (2003)

Assessment Of Retran-3D Boiling Models Against Experimental Subcooled Boiling Tube Data
R. Macian, P. Coddington, P. Stangroom
Nuclear Technology, Vol. 142, 47-63 (2003)

Interpretation Of Experimental Results From Moderate-Power In-Pile Testing Of A Pu-Er-Zr-Oxide Inert Matrix Fuel
Hellwig Ch., Kasemeyer U., Ledergerber G., Byung-Ho Lee, Young-Woo Lee, Chawla R.
Annals of Nuclear Energy 30, 287-299 (2003)

Planned Experimental Studies On Natural Circulation And Stability Performance Of Boiling Water Reactors In Four Experimental Facilities And First Results (Nacusp)
De Kruijf W.J.M., Katelaar K.C.J, Avakian G., Gubernatis P., Caruge D., Manera A., Van Der Hagen T.H.J.J., Yadigaroglu G., Domenicus G., Rohde U., Prasser H.-M., Castrillo F., Huggenberger M., Hennig D., Munoz-Cobo J.L., Aguirre C.
Nuclear Engineering And Design, 221, 241-250 (2003)

Analysis And Sensitivity Studies Of Postulated Sb-Locas In The Mühleberg (Kkm) BWR/4 By Trac-Bf1
G. Analytis, Coddington. Th,
Annals of Nuclear Energy, 29, 1525-1549 (2002)

Core loss during a severe accident (COLOSS)
B. Adroguer, P. Chatelard, J.P. van Dorsselaere, C. Duriez, N. Cocuaud, L. Bellenfant, D. Bottomley, V. Vrtilkova, K. Müller, W. Hering, C. Homann, W. Krauss, A. Miassoedov, M. Steinbrück, J. Stuckert, Z. Hozer, G. Bandini, J.C. Birchley, T. von Berlepsch, M. Buck, J.A.F. Benitez, E. Virtanen, S. Marguet, G. Azarian, H. Plank, M. Veshchunov, Y. Zvonarev, A. Goryachev
Nuclear Engineering and Design 221, 55
http://dx.doi.org/10.1016/S0029-5493(02)00344-8

A Novel Auto-Correlation Function Method For The Determination Of The Decay Ratio In BWR Stability Analysis
K. Behringer, D. Hennig
Annals of Nuclear Energy, 29, 1483-1504 (2002)

A Study Of The Performance Of Void Fraction Correlations Used In The Context Of Drift-Flux Two-Phase Flow Models
P. Coddington, R. Macian
Nuclear Engineering And Design, 215, 199-216

Application And In-Depth Assessment Of Retran-3d For Best Estimate Analysis Of Nuclear Power Plant Transients
P. Coddington, R. Macian, M. Zimmermann, Chawla. A,
Journal of Nuclear Science And Technology, 39-9, 972-985 (2002)

Simulation And Analysis Of Experimental Blow Down And Small-Break Loss-Of-Coolant Scenarios With Retran-3D
R. Macian, P. Coddington
Nuclear Technology, Vol. 139, 185-204 (2002)

A Nodal Modal Method For The Neutron Diffusion Equation. Application To BWR Stability Analysis
R. Miro, D. Ginestar, G. Verdu, D. Hennig
Annals of Nuclear Energy, 29, 1171-1194 (2002)

On The Feasibility Of Ads-Representative Integral Experiments Using Limited Amounts Of Low-Enriched U-Fuel
S. Pelloni, R. Chawla
Journal of Nuclear Science And Technology, Supplement 2, 1224-1227 (2002)

Data Sensitivity Of Design Calculations For High Conversion D2o Reactors
S. Pelloni, H. Hager, O. Joneja, Chawla. P,
Journal of Nuclear Science And Technology, Supplement 2, 880-883 (2002)

The Physical Mechanism Of Core-Wide And Local Instabilities At The Forsmark-1 BWR
G. Analytis, Hennig. Th, H. D, K. Karlsson,
Nuclear Engineering And Design, Vol. 205, Pp. 91-105, 2001.

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2000 and before

A Study Of Boiling Water Reactor Stability Behaviour
D. Hennig
Nuclear Technology, Vol. 126, Pp 10-31, (1999)

Implementation Of An Improved Interfacial Mass And Energy Transfer Model In Retran-3d
R. Macian, P. Cebull, P. Coddington, M. Paulsen
Nuclear Technology, Vol. 128, Pp 139-152, (1999)

Evaluation Of The Slip Option In Retran-3d
D. Maier, P. Coddington
Nuclear Technology, Vol. 128, Pp 153-168, (1999)

Vipre-02 Subchannel Validation Against Nupec Bwr Void Fraction Data
Y. Aounallah, P. Coddington
Nuclear Technology, Vol. 128, Pp 225-232, (1999)

Fuel-Temperature Coefficient For Boiling Water Reactor Transient Calculations: Its Dependence On Reactor Conditions
J.M. Kallfelz, L.A. Belblidia, P. Grimm
Nuclear Science And Engineering 121 (1995), 301-311

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Nuclear Energy and Safety (NES)

Laboratory for Reactor Physics and Thermal-Hydraulics (LRT)
Paul Scherrer Institute
5232 Villigen PSI
Switzerland

Hakim Ferroukhi
Head of the Laboratory
Office: OHSA/C10
Telephone: +41 56 310 4062
E-mail: hakim.ferroukhi@psi.ch

Petra Kull
Administration and Assistance
Office: OHSA/C18
Telephone: + 41 56 310 2685
E-mail: petra.kull@psi.ch

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