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Journal Publications

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
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 by neutron noise technique
Presented at: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019); August 25-29, 2019; Portland, OR, USA.
DORA PSI
Hursin M, Park J, Kim W, Siefman D, Perret G, Vasiliev A, et al.
Uncertainty quantification of LWR-proteus phase II experiments using CASMO-5
Presented at: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019); August 25-29, 2019; Portland, OR, USA.
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. 2019. https://doi.org/10.1016/j.net.2019.07.010
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. https://doi.org/10.1080/00295450.2019.1591154
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. https://doi.org/10.3390/ma12030494
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 8th 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
Casanovas A, Domingo-Pardo C, Guerrero C, Lerendegui-Marco J, Calviño F, Tarifeño-Saldivia A, et al.
Measurement of the radiative capture cross section of the s-process branching points ²⁰⁴Tl and ¹⁷¹Tm at the n_TOF facility (CERN)
In: Sun Y, ed. 16th international symposium on capture gamma-ray spectroscopy and related topics (CGS16). Vol. 178. EPJ web of conferences. sine loco: EDP Sciences; 2018. https://doi.org/10.1051/epjconf/201817803004
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
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
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
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
The European Physical Journal A. 2018; 54(5): 82. 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
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
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
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
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 DA
Cross-observables and cross-isotopes correlations in nuclear data from integral constraints
EPJ Nuclear Sciences and Technologies. 2018; 4: 35. https://doi.org/10.1051/epjn/2018011
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
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, Ferroukhi H, Perret G
Nuclear data correlation between different isotopes via integral information
EPJ Nuclear Sciences and Technologies. 2018; 4: 7. https://doi.org/10.1051/epjn/2018006
DORA PSI
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. https://doi.org/10.1051/epjn/2018005
DORA PSI
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
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
Chollet M, Cozzo C, Bertsch J, Martin M, Grolimund D
NEW INSIGHTS IN THE FUEL GRAIN SUBDIVISION DURING IN-PLANT IRRADIATION UP TO HIGH BURN-UP
Presented at: 2017 water reactor fuel performance meeting; September 10-14, 2017; Jeju, Korea.
DORA PSI
Chollet M, 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. https://doi.org/10.1051/epjn/2016040
DORA PSI
Cozzo C, Bertsch J, Fave L, Dokhane A, Krack M, Pouchon M, et al.
SiC CLADDING BEHAVIOR: EXPERIMENTS AND MODELLING AT PSI
Presented at: 2017 water reactor fuel performance meeting; September 10-14, 2017; Jeju, Korea.
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
Dokhane A, Leray O, Rochman D, Vasiliev A, Ferroukhi H
Nuclear Data Uncertainty Decomposition for SPERT-III RIA Experiments using SIMULATE-3K and SHARK-X
In: M&C 2017 international conference on mathematics & computational methods applied to nuclear science & engineering. Vol. P236. ; 2017.
DORA PSI
Dokhane A, Pecchia M, Ferroukhi H, Pautz A
SIMULATE-3K Analyses of Neutron Noise Response to Fuel Assembly Vibrations and Thermal-Hydraulics Parameters Fluctuations
In: M&C 2017 international conference on mathematics & computational methods applied to nuclear science & engineering. Vol. P289. ; 2017.
DORA PSI
Edwards L, LeBlanc D, Rodenburg C, Uhlíř J, Dai Z, Lauritzen B, et al.
Worldwide activities
In: Dolan TJ, ed. Molten salt reactors and thorium energy. Cambridge: Elsevier; 2017. https://doi.org/10.1016/B978-0-08-101126-3.00026-9
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
Fleming M, Sublet J-C, Gilbert MR, Koning A, Rochman D
TALYS/TENDL verification and validation processes: Outcomes and recommendations
Presented at: 2016 international conference on nuclear data for science and technology, ND 2016; September 11-16, 2016. https://doi.org/10.1051/epjconf/201714602033
DORA PSI
Griffin P, Rochman D, Koning A
Characterization of the energy-dependent uncertainty and correlation in silicon neutron displacement damage metrics
Presented at: 2016 international conference on nuclear data for science and technology, ND 2016; September 11-16, 2016. https://doi.org/10.1051/epjconf/201714602008
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
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
Herrero JJ, Rochman D, Leray O, Vasiliev A, Pecchia M, Ferroukhi H, et al.
Impact of nuclear data uncertainty on safety calculations for spent nuclear fuel geological disposal
Presented at: 2016 international conference on nuclear data for science and technology, ND 2016; September 11-16, 2016. https://doi.org/10.1051/epjconf/201714609028
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
Hursin M, Leray O, Perret G, Pautz A, Bostelmann F, Aures A, et al.
Impact of implicit effects on uncertainties and sensitivities of the Doppler coefficient of a LWR pin cell
Presented at: 2016 international conference on nuclear data for science and technology, ND 2016; September 11-16, 2016. https://doi.org/10.1051/epjconf/201714609034
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
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
Leray O, Rochman D, Fleming M, Sublet J-C, Koning A, Vasiliev A, et al.
Fission yield covariances for JEFF: A Bayesian Monte Carlo method
Presented at: 2016 international conference on nuclear data for science and technology, ND 2016; September 11-16, 2016. https://doi.org/10.1051/epjconf/201714609023
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
Mala P, Pautz A, Canepa S, Ferroukhi H
Nodal and Pin-by-pin Calculations Comparison with Codes SIMULATE-5 and DYN₃D
In: M&C 2017 international conference on mathematics & computational methods applied to nuclear science & engineering. Vol. P010. ; 2017.
DORA PSI
Mukin R, Clifford I, Ferroukhi H, Seidl M
Thermal hydraulic analysis of PWR Assembly bowing using subchannel Code Cobra-TF
In: 17th international topical meeting on nuclear reactor thermal hydraulics, NURETH 2017. Vol. 2017-September. Association for Computing Machinery, Inc; 2017.
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
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, Mala P, Ferroukhi H, Vasiliev A, Li J
Bowing effects on power and burn-up distributions for simplified full PWR and BWR cores
In: M&C 2017 international conference on mathematics & computational methods applied to nuclear science & engineering. Vol. P286. ; 2017.
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
Rochman D, Koning AJ, Sublet JC, Fleming M, Bauge E, Hilaire S, et al.
The TENDL library: Hope, reality and future
Presented at: 2016 international conference on nuclear data for science and technology, ND 2016; September 11-16, 2016. https://doi.org/10.1051/epjconf/201714602006
DORA PSI
Sjöstrand H, Conroy S, Helgesson P, Hernandez SA, Koning A, Pomp S, et al.
Propagation of nuclear data uncertainties for fusion power measurements
Presented at: 2016 international conference on nuclear data for science and technology, ND 2016; September 11-16, 2016. https://doi.org/10.1051/epjconf/201714602034
DORA PSI
Yin W-J, Krack M, Li X, Chen L-Z, Liu L-M
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
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
Bocharov D, Krack M, Kalinko A, Purans J, Rocca F, Ali SE, et al.
Ab initio molecular dynamics simulations of the Sc K-edge EXAFS of scandium trifluoride
Presented at: 16th international conference on X-ray absorption fine structure, XAFS 2015; August 23-28, 2015. https://doi.org/10.1088/1742-6596/712/1/012009
DORA PSI
Bocharov D, Chollet M, Krack M, Bertsch J, Grolimund D, Martin M, et al.
Interpretation of the U L3-edge EXAFS in uranium dioxide using molecular dynamics and density functional theory simulations
Presented at: 16th international conference on X-ray absorption fine structure, XAFS 2015; August 23-28, 2015. https://doi.org/10.1088/1742-6596/712/1/012091
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
Cozzo C, Epiney A, Canepa S, Ferroukhi H, Zerkak O, Khvostov G, et al.
Full core LOCA analysis for BWR/6 - Methodology and first results
In: Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance. Vol. 1. American Nuclear Society; 2016.
DORA PSI
Dokhane A, Ferroukhi H, Pautz A
On Causality Analysis of Nuclear Reactor Noise using Partial Directed Coherence
Presented at: Physics of reactors 2016: unifying theory and experiments in the 21st century, PHYSOR 2016.
DORA PSI
Dokhane A, Leray O, Rochman D, Ferroukhi H, Pautz A
Validation of SIMULATE-3K against SPERT-III Ria Experiments with Quantification of Nuclear Data Uncertainties
Presented at: Physics of reactors 2016: unifying theory and experiments in the 21st century, PHYSOR 2016.
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
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
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; 1: 1-9. https://doi.org/10.1016/j.forsciint.2015.09.019
DORA PSI
Grimm P, Hursin M, Perret G, Siefman D, Ferroukhi H
CASMO-5 analysis of reactivity worths of burnt PWR fuel samples measured in LWR-proteus PHASE II
Presented at: Physics of reactors 2016: unifying theory and experiments in the 21st century, PHYSOR 2016; May 1-5, 2016.
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, Siefman D, Perret G, Grimm P, Pautz A
Verification of the new implementations in SHARK-X for reactivity coefficients and relative reactivity worth UQ
Presented at: Physics of reactors 2016: unifying theory and experiments in the 21st century, PHYSOR 2016; May 1-5, 2016.
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, Ferroukhi H, Pautz A
Comparison of Fission Yield Perturbation Methodologies on Nuclide Composition for a PWR UO₂ Fuel Assembly
Presented at: Physics of reactors 2016: unifying theory and experiments in the 21st century, PHYSOR 2016.
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
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
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
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
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
Vasiliev A, Ferroukhi H, Pautz A
Solution of the Beavrs Benchmark using CASMO-5 / SIMULATE-5 Code Sequence
Presented at: Physics of reactors 2016: unifying theory and experiments in the 21st century, PHYSOR 2016.
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. https://doi.org/10.1038/srep23298
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
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
Brankov V, Khvostov G, Mikityuk K, Pautz A, Restani R, Abolhassani S
Modeling of Axial Distribution of Released Fission Gas in KKL BWR Fuel Rods during Base Irradiation
Presented at: TopFuel 2015: reactor fuel performance; Sep 13-17, 2015; Zuerich, Switzerland.
DORA PSI
Canepa S, Krack M, Ferroukhi H, Pautz A
Scalability Benchmarking Methodology for Hybrid Parallel Core Calculations with the Code nTRACER
In: M&C + SNA + MC 2015: joint international conference on mathematics and computation (M&C), supercomputing in nuclear applications (SNA) and the Monte Carlo (MC) method. Vol. 2015. ; 2015.
DORA PSI
Chollet M, Cozzo C, Bertsch J
Positron annihilation spectroscopy study of lattice defects in non-irradiated doped and un-doped fuels
Presented at: TopFuel 2015: reactor fuel performance; Sep 13-17, 2015; Zuerich, Switzerland.
DORA PSI
Chollet M, Krack M, Kuzmin A, Bertsch J, Grolimund D, Martin M
Theoretical modelling of pristine and chromium-doped UO₂
Presented at: E-MRS 2015; May 11-15, 2015; Lille, France.
DORA PSI
Dokhane A, Ferroukhi H
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
Dokhane A, Zerkak O, Ferroukhi H, Gajev I, Judd J, Kozlowski T
Trace/simulate-3k analysis of the NEA/OECD oskarshamn-2 stability benchmark
In: NURETH 16: proceedings of the 16th international topical meeting on nuclear reactor thermal-hydraulics. Vol. 6. International topical meeting on nuclear reactor thermal hydraulics 2015, NURETH 2015. American Nuclear Society; 2015.
DORA PSI
Epiney A, Canepa S, Zerkak O, Ferroukhi H
Towards a consolidated approach for the validation of plant system codes and models: Case study for a Bwr fast depressurisation event
In: NURETH 16: proceedings of the 16th international topical meeting on nuclear reactor thermal-hydraulics. Vol. 3. International topical meeting on nuclear reactor thermal hydraulics 2015, NURETH 2015. American Nuclear Society; 2015.
DORA PSI
Hursin M, Ferroukhi H, Pautz A
BWR Full Core Analysis with SERPENT/SIMULATE-3 Hybrid Stochastic/Determinstic Code Sequence
In: M&C + SNA + MC 2015: joint international conference on mathematics and computation (M&C), supercomputing in nuclear applications (SNA) and the Monte Carlo (MC) method. Vol. 63. ; 2015.
DORA PSI
Krack M
On the ground state electronic structure of uranium dioxide
Physica Scripta. 2015; 90(9): 94014. https://doi.org/10.1088/0031-8949/90/9/094014
DORA PSI
Leray O, Pecchia M, Vasiliev A, Ferroukhi H, Pautz A
Development, Verification and Test Application of a Hybrid CASMO-5/SERPENT Depletion Scheme
In: M&C + SNA + MC 2015: joint international conference on mathematics and computation (M&C), supercomputing in nuclear applications (SNA) and the Monte Carlo (MC) method. Vol. 2015. ; 2015.
DORA PSI
Mala P, Canepa S, Ferroukhi H, Pautz A
Preparation of Pin-By-Pin Nuclear Libraries with Superhomogenization Method for Ntracer and Dort Core Calculations
In: M&C + SNA + MC 2015: joint international conference on mathematics and computation (M&C), supercomputing in nuclear applications (SNA) and the Monte Carlo (MC) method. Vol. 2015. ; 2015.
DORA PSI
Mikityuk K, Khvostov G
Benchmark on behavior of MOX fuel pin under irradiation at nominal power in sodium fast reactor
Presented at: TopFuel 2015: reactor fuel performance; Sep 13-17, 2015; Zuerich, Switzerland.
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. https://doi.org/10.1088/0953-8984/27/45/455401
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, Herrero JJ, Ferroukhi H, Vasiliev A, Canepa S, Pautz A
COMPLINK: a versatile tool for automatizing the representation of material data in MCNP models
In: ICNC 2015 - international conference on nuclear criticality safety. Vol. 1. sine loco: American Nuclear Society; 2015.
DORA PSI
Pecchia M, Ferroukhi H, Canepa S, Vasiliev A
Computational Scheme for Burnup Credit applied to Long Term Waste Disposal
In: ICNC 2015: International Cooperation in Nuclear Criticality Safety. Vol. 1. ; 2015.
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
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
The European Physical Journal A. 2015; 51(12): 182. https://doi.org/10.1140/epja/i2015-15182-0
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
Vasiliev A, Zhu T, Pecchia M, Ferroukhi H, Pautz A
Towards Application of Neutron Cross-Section Uncertainty Propagation Capability in the Criticality Safety Methodology
In: ICNC 2015: International Cooperation in Nuclear Criticality Safety. Vol. 1. ; 2015.
DORA PSI
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
Wicaksono D, Zerkak O, Pautz A
A methodology for global sensitivity analysis of transient code output applied to a reflood experiment model using trace
In: NURETH 16: proceedings of the 16th international topical meeting on nuclear reactor thermal-hydraulics. Vol. 6. International topical meeting on nuclear reactor thermal hydraulics 2015, NURETH 2015. American Nuclear Society; 2015.
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
Zhu T, Vasiliev A, Ferroukhi H, Pautz A
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
Canepa S, Ferroukhi H, Pautz A
EFFECTS OF ADVANCED RADIAL SUBMESHING METHODS ON PIN POWER RECONSTRUCTION FOR AN EPR CORE DESIGN
Presented at: PHYSOR 2014: the role of reactor physics toward a sustainable future.
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
Dokhane A, Ferroukhi H, Pautz A
ANALYSIS OF THE OECD/NEA OSKARSHAMN-2 FEEDWATER TRANSIENT AND STABILITY BENCHMARK WITH SIMULATE-3K
Presented at: PHYSOR 2014: the role of reactor physics toward a sustainable future.
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
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(1): 498-501. https://doi.org/10.1016/j.nds.2014.04.117
DORA PSI
Grimm P, Perret G, Ferroukhi H
CASMO-4E AND CASMO-5 ANALYSIS OF THE ISOTOPIC COMPOSITIONS OF THE LWR-PROTEUS PHASE II BURNT PWR UO₂ FUEL SAMPLES
Presented at: PHYSOR 2014: the role of reactor physics toward a sustainable future.
DORA PSI
Hursin M, Ferroukhi H, Pautz A
Neutronic Data Generation for BWR Models, Comparison OF SERPENT and CASMO-5
Presented at: ANS student conference 2014; April 3-6, 2014; University Park, PA, USA.
DORA PSI
Khvostov G, Mikityuk K, Pautz A
Analysis of Axial Fuel Relocation Based on Gamma Scan Data from OECD Halden Reactor Project LOCA Tests
In: WRFPM 2014 proceedings. ; 2014.
DORA PSI
Leray O, Grimm P, Ferroukhi H, Pautz A
QUANTIFICATION OF CODE, LIBRARY AND CROSS-SECTION UNCERTAINTY EFFECTS ON THE VOID REACTIVITY COEFFICIENT OF A BWR UO₂ ASSEMBLY
Presented at: PHYSOR 2014: the role of reactor physics toward a sustainable future.
DORA PSI
Leray O, Pecchia M, Vasiliev A, Ferroukhi H, Pautz A
Reactivity benchmark Analysis and Code Reactivity Prediction for a PWR Fuel Assembly
Presented at: ANS student conference 2014; April 3-6, 2014; University Park, PA, USA.
DORA PSI
Leray O, Ferroukhi H
UNCERTAINTY AND SENSITIVITY ANALYSIS OF OECD/NEA UAM FUEL THERMAL BEHAVIOUR BENCHMARK USING A FALCON/URANIE METHODOLOGY
Presented at: PHYSOR 2014: the role of reactor physics toward a sustainable future.
DORA PSI
Leray O, Grimm P, Hursin M, Ferroukhi H, Pautz A
UNCERTAINTY QUANTIFICATION OF SPENT FUEL NUCLIDE COMPOSITIONS DUE TO CROSS SECTIONS, DECAY CONSTANTS AND FISSION YIELDS
Presented at: PHYSOR 2014: the role of reactor physics toward a sustainable future.
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(1): 108-112. https://doi.org/10.1016/j.nimb.2013.09.043
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
Ngayam-Happy R, Krack M
Radiation damage characterization in non-stoichiometric uranium dioxide by molecular dynamics simulations
In: SNA + MC 2013 - JOINT INTERNATIONAL CONFERENCE ON SUPERCOMPUTING IN NUCLEAR APPLICATIONS + MONTE CARLO. ; 2014. https://doi.org/10.1051/snamc/201401301
DORA PSI
Pecchia M, Vasiliev A, Leray O, Ferroukhi H, Pautz A
NEW PSI METHODOLOGY FOR MANUFACTURING AND TECHNOLOGICAL UNCERTAINTY QUANTIFICATION
Presented at: PHYSOR 2014: the role of reactor physics toward a sustainable future.
DORA PSI
Pecchia M, Vasiliev A, Ferroukhi H, Pautz A
UPDATED VALIDATION OF THE PSI CRITICALITY SAFETY EVALUATION METHODOLOGY USING MCNPX2.7 AND ENDF/B-VII.1
Presented at: PHYSOR 2014: the role of reactor physics toward a sustainable future.
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(1): 575-578. https://doi.org/10.1016/j.nds.2014.04.139
DORA PSI
Vasiliev A, Ferroukhi H, Pautz A
Validation Enhancements of the PSI Fast Neutron Fluence Computational Scheme using Operational PWR Experimental Data
Presented at: ANS student conference 2014; April 3-6, 2014; University Park, PA, USA.
DORA PSI
Wicaksono D, Grimm P, Vasiliev A, Hursin M, Perret G, Ferroukhi H
VALIDATION OF TWO MONTE CARLO CODES FOR LWR BURNUP CALCULATIONS
Presented at: PHYSOR 2014: the role of reactor physics toward a sustainable future.
DORA PSI
Zhu T, Vasiliev A, Ferroukhi H, Pautz A
Application of the PSI-NUSS Tool for the Estimation of Nuclear Data Related keff Uncertainties for the OECD/NEA WPNCS UACSA Phase I Benchmark
Nuclear Data Sheets. 2014; 118(1): 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(1): 388-391. https://doi.org/10.1016/j.nds.2014.04.088
DORA PSI
Canepa S, Zerkak O, Ferroukhi H, Pautz A
Post-Analysis of a Turbine Trip Test at a BWR/6 using the TRACE/S3K Coupled Code
In: Proceedings of the 15th international topical meeting on nuclear reactor thermal-hydraulics. ; 2013.
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
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, Vasiliev A, Ferroukhi H, Pautz A
Comparison of serpent and CASMO-5M for pressurized water reactors models
In: International conference on mathematics and computational methods applied to nuclear science and engineering, M and C 2013. Vol. 3. ; 2013.
DORA PSI
Khvostov G, Pautz A, Kolstad E, Ledergerber G
Analysis of a Halden LOCA test with the BWR high burnup fuel
In: LWR fuel performance meeting (Top Fuel 2013). sine loco: American Nuclear Society (ANS); 2013.
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
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(43160): 143-152. https://doi.org/10.1016/j.jnucmat.2013.04.081
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
Wicaksono D, Zerkak O, Nikitin K, Ferroukhi H, Chawla R
Application of power time-projection on the operator-splitting coupling scheme of the trace/S3K coupled code
In: International conference on mathematics and computational methods applied to nuclear science and engineering, M and C 2013. Vol. 3. ; 2013.
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. https://doi.org/10.1155/2013/549793
DORA PSI
Devynck F, Iannuzzi M, Krack M
Frenkel pair recombinations in UO 2: Importance of explicit description of polarizability in core-shell molecular dynamics simulations
Physical Review B. 2012; 85(18): 184103. https://doi.org/10.1103/PhysRevB.85.184103
DORA PSI
Dokhane A, Canepa S, Ferroukhi H
Transition to CASMO-5M and SIMULATE-3K for Stability Analyses of the Swiss BWRs
Presented at: PHYSOR 2012: advances in reactor physics - linking research, industry, and education.
DORA PSI
Ferroukhi H, Vasiliev A, Dufresne A, Chawla R
Towards a reference numerical scheme using MCNPX for PWR control rod tip fluence estimations
In: International conference on the physics of reactors 2012, PHYSOR 2012: advances in reactor physics. Vol. 1. ; 2012.
DORA PSI
Giust FD, Grimm P, Chawla R
Experimental validation of 3D reconstructed pin-power distributions in full-scale BWR fuel assemblies with partial length rods
In: International conference on the physics of reactors 2012, PHYSOR 2012: advances in reactor physics. Vol. 1. ; 2012.
DORA PSI
Grimm P, Perret G
Experimental validation of CASMO-4E and CASMO-5M for radial fission rate distributions in a westinghouse SVEA-96 Optima2 BWR fuel assembly
In: International conference on the physics of reactors 2012, PHYSOR 2012: advances in reactor physics. Vol. 4. ; 2012.
DORA PSI
Grimm P, Vasiliev A, Ferroukhi H
REACTOR PHYSICS STUDIES FOR ASSESSMENT OF TRAMP URANIUM METHODS
Presented at: PHYSOR 2012: advances in reactor physics - linking research, industry, and education.
DORA PSI
Krack M
Atomistic simulation of nuclear fuels
Presented at: 2011 MRS Fall Meeting; November 28 - December 2, 2011; Boston, MA. https://doi.org/10.1557/opl.2012.520
DORA PSI
Wieselquist W, Vasiliev A, Ferroukhi H
Nuclear data uncertainty propagation in a lattice physics code using stochastic sampling
In: International conference on the physics of reactors 2012, PHYSOR 2012: advances in reactor physics. Vol. 4. ; 2012.
DORA PSI
Zhu T, Vasiliev A, Wieselquist W, Ferroukhi H
Stochastic sampling method with MCNPX for nuclear data uncertainty propagation in criticality safety applications
In: International conference on the physics of reactors 2012, PHYSOR 2012: advances in reactor physics. Vol. 1. ; 2012.
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 Ge 2Sb2Te5
Journal of Physics: Condensed Matter. 2011; 23(26): 265801. https://doi.org/10.1088/0953-8984/23/26/265801
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. 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): 815-825. https://doi.org/10.1016/j.nucengdes.2011.01.007
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
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
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
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
Yun Y, Khvostov G, Freixa J, Zimmermann MA
Analysis of fuel rod behaviour in a EPR^TM during the base irradiation and LOCA-transient utilizing the FALCON code
In: Proceedings of the 2010 LWR fuel performance/top fuel/WRFPM. sine loco: American Nuclear Society; 2011.
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
Borisenko SV, Zabolotnyy VB, Evtushinsky DV, Kim TK, Morozov IV, Yaresko AN, et al.
Superconductivity without nesting in LiFeAs
Physical Review Letters. 2010; 105(6): 67002. https://doi.org/10.1103/PhysRevLett.105.067002
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
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
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
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
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

Preliminary Assessment of Criticality Safety Constraints for Swiss Spent Nuclear Fuel Loading in Disposal Canisters
A. Vasiliev, J. Herrero, M. Pecchia, D. Rochman, H. Ferroukhi, S. Caruso
Materials 2019, 12, 494
https://doi.org/10.3390/ma12030494

Studies of intra-pin power distributions in operated BWR fuel assemblies using MCNP with a cycle check-up methodology
M. Pecchia, H. Ferroukhi, A. Vasiliev, P. Grimm
Annals of Nuclear Energy 129 (2019) 67-78
https://doi.org/10.1016/j.anucene.2019.01.047

Enhancements along with application of the Asymptotic Progressing nuclear data Incremental Adjustment (APIA) methodology by individual assimilations of fast reactor data
S. Pelloni, D. Rochman
Annals of Nuclear Energy 129 (2019) 79–89
https://doi.org/10.1016/j.anucene.2019.01.057

Stochastic vs. sensitivity-based integral parameter and nuclear data adjustments
D. Siefman, M. Hursin, D. Rochman, S. Pelloni, A. Pautz
Eur. Phys. J. Plus (2018) 133-429
https://link.springer.com/content/pdf/10.1140%2Fepjp%2Fi2018-12303-8.pdf

TENDL: Complete Nuclear Data Library for Innovative Nuclear Science and Technology
A.J. Koning, D. Rochman, J.-Ch. Sublet, N. Dzysiuk, M. Fleming, S. Van Der Marck
Nuclear Data Sheets 155 (2019) 1–55
https://doi.org/10.1016/j.nds.2019.01.002

BWR-4 ATWS modeling with RELAP5-S3K
K. Nikitin, P. Mueller, A. Bruder, S. Walser, J. Judd, D. Hiltbrand
Nuclear Engineering and Design 344 (2019) 38-45
https://doi.org/10.1016/j.nucengdes.2019.01.023

Impact of Nuclear Data Uncertainty in the Modeling of Neutron-Induced Recoil Atom Energy Distributions in Silicon
P.J. Griffin, J. Koning, D. Rochman
IEEE Nuclear and Plasma Society, January 2019, Pages 1
https://ieeexplore.ieee.org/abstract/document/8625464

Simulation of the microfluidic mixing and the droplet generation for 3D printing of nuclear fuels
A. Shama, M. Pouchon, I. Clifford
Additive Manufacturing, Volume 26, March 2019, Pages 1-14
https://doi.org/10.1016/j.addma.2018.12.011

Neutron noise analysis of simulated mechanical and thermal-hydraulic perturbations in a PWR core
L. A. Torres, D. Chionis, C. Montalvo, A. Dokhane, A. García-Berrocal
Annals of Nuclear Energy 126 (2019) 242–252
https://doi.org/10.1016/j.anucene.2018.11.032