LRT Publication List (since 2018)
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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/https://doi.org/10.1016/j.nucengdes.2020.111017
DORA PSI -
Alcayne V, Mendoza E, Cano-Ott D, Kimura A, Aberle O, Amaducci S, et al.
Measurement of the 244Cm capture cross sections at both CERN n_TOF experimental areas
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Sine loco: EDP Science; 2020:01034 (5 pp.). https://doi.org/10.1051/epjconf/202023901034
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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 -
Alhassan E, Rochman D, Vasiliev A, Bergmann RM, Wohlmuther M, Koning AJ, et al.
In search of the best nuclear data file for proton induced reactions: varying both models and their parameters
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Sine loco: EDP Science; 2020:13005 (4 pp.). https://doi.org/10.1051/epjconf/202023913005
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Andreani M, Kapulla R, Kelm S, Paladino D, Paranjape S
Analyses of gas stratification erosion by a vertical jet in presence of an obstacle using the GOTHIC code
Journal of Nuclear Engineering and Radiation Science. 2020; 6(2): 021110 (18 pp.). https://doi.org/10.1115/1.4046296
DORA PSI -
Andreani M, Paranjape S
Gas mixing caused by interacting heat sources. Part ii: modelling
Nuclear Engineering and Design. 2020; 370: 110887 (16 pp.). https://doi.org/10.1016/j.nucengdes.2020.110887
DORA PSI -
Babiano-Suarez V, Aberle O, Alcayne V, Amaducci S, Andrzejewski J, Audouin L, et al.
80Se(n,γ) cross-section measurement at CERN n_TOF
In: Nuclear physics in astrophysics IX (NPA-IX), 15-20 September 2019, Frankfurt, Germany. Vol. 1668. Journal of physics: conference series. Bristol, United Kingdom: IOP Publishing; 2020:012001 (8 pp.). https://doi.org/10.1088/1742-6596/1668/1/012001
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Bernal A, Pecchia M, Rochman D, Vasiliev A, Ferroukhi H
Methodology for high-fidelity deterministic modelling of Swiss LWR fuel assemblies
In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1197 (8 pp.).
DORA PSI -
Betschart T, Lind T, Prasser H-M
Investigation of two-phase flow hydrodynamics under SGTR severe accident conditions
Nuclear Engineering and Design. 2020; 366: 110768 (14 pp.). https://doi.org/10.1016/j.nucengdes.2020.110768
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Casanovas A, Tarifeño-Saldivia AE, Domingo-Pardo C, Calviño F, Maugeri E, Guerrero C, et al.
Neutron capture measurement at the n_TOF facility of the 204Tl and 205Tl s-process branching points
In: Nuclear physics in astrophysics IX (NPA-IX), 15-20 September 2019, Frankfurt, Germany. Vol. 1668. Journal of physics: conference series. Bristol, United Kingdom: IOP Publishing; 2020:012005 (9 pp.). https://doi.org/10.1088/1742-6596/1668/1/012005
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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
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Choi YJ, Kam DH, Padopoulos P, Lind T, Jeong YH
Experimental investigation on bubble behaviors in a water pool using the venturi scrubbing nozzle
Nuclear Engineering and Technology. 2020. https://doi.org/10.1016/j.net.2020.11.024
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Domingo-Pardo C, Babiano-Suarez V, Balibrea-Correa J, Caballero L, Ladarescu I, Lerendegui-Marco J, et al.
Review and new concepts for neutron-capture measurements of astrophysical interest
In: Nuclear physics in astrophysics IX (NPA-IX), 15-20 September 2019, Frankfurt, Germany. Vol. 1668. Journal of physics: conference series. sine loco: IOP Publishing; 2020:012013 (13 pp.). https://doi.org/10.1088/1742-6596/1668/1/012013
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Eleme Z, Patronis N, Stamatopoulos A, Tsinganis A, Kokkoris M, Michalopoulou V, et al.
First results of the 241Am(n,f) cross section measurement at the experimental area 2 of the n_TOF facility at CERN
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Sine loco: EDP Science; 2020:05014 (5 pp.). https://doi.org/10.1051/epjconf/202023905014
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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 -
Herranz LE, Pellegrini M, Lind T, Sonnenkalb M, Godin-Jacqmin L, López C, et al.
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF) Phase 2 - results of severe accident analyses for Unit 1
Nuclear Engineering and Design. 2020; 369: 110849 (7 pp.). https://doi.org/10.1016/j.nucengdes.2020.110849
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Hombourger B, Křepel J, Pautz A
The EQL0D fuel cycle procedure and its application to the transition to equilibrium of selected molten salt reactor designs
Annals of Nuclear Energy. 2020; 144: 107504 (18 pp.). https://doi.org/10.1016/j.anucene.2020.107504
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Hursin M, Rochman D, Vasiliev A, Ferroukhi H, Pautz A
Impact of various source of covariance information on integral parameters uncertainty during depletion calculations with CASMO-5
In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1172 (10 pp.).
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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
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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
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Hursin M, Pakari O, Perret G, Frajtag P, Lamirand V, Pázsit I, et al.
Validation of axial void profile measured by neutron noise techniques in CROCUS
In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1173 (8 pp.).
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Jäckel BS, Steiner P, Klügel J-U
Loss-of-cooling accident calculations for the wet storage pool of NPP Gösgen/Däniken
Nuclear Engineering and Design. 2020; 370: 110839 (6 pp.). https://doi.org/10.1016/j.nucengdes.2020.110839
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Kalilainen J, Nichenko S, Krepel J
Evaporation of materials from the molten salt reactor fuel under elevated temperatures
Journal of Nuclear Materials. 2020; 533: 152134 (13 pp.). https://doi.org/10.1016/j.jnucmat.2020.152134
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
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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
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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
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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
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Lamirand V, Rais A, Pakari O, Hursin M, Laureau A, Polhus J, et al.
Analysis of the first COLIBRI fuel rods oscillation campaign in the CROCUS reactor for the European project CORTEX
In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1573 (9 pp.).
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Lind T, Campbell S, Herranz LE, Kissane M, Song JH
A summary of fission-product-transport phenomena during SGTR severe accidents
Nuclear Engineering and Design. 2020; 363: 110635 (10 pp.). https://doi.org/10.1016/j.nucengdes.2020.110635
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
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Mala P, Pautz A, Ferroukhi H, Vasiliev A
Development of 3D pin-by-pin core solver tortin and coupling with thermal-hydraulics
In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1583 (8 pp.).
DORA PSI -
Manna A, Aberle O, Alcayne V, Amaducci S, Andrzejewski J, Audouin L, et al.
Setup for the measurement of the 235U(n,f) cross section relative to n-p scattering up to 1 GeV
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Sine loco: EDP Science; 2020:01008 (5 pp.). https://doi.org/10.1051/epjconf/202023901008
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Mastromarco M. M, Mazzone A, Massimi C, Cristallo S, Colonna N, Aberle O, et al.
The 154Gd neutron capture cross section measured at the n_TOF facility and its astrophysical implications
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Sine loco: EDP Science; 2020:07003 (5 pp.). https://doi.org/10.1051/epjconf/202023907003
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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
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Mengoni A, Damone LA, Barbagallo M, Aberle O, Alcayne V, Amaducci S, et al.
New reaction rates for the destruction of 7Be during big bang nucleosynthesis measured at CERN/n_TOF and their implications on the cosmological lithium problem
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Sine loco: EDP Science; 2020:07001 (4 pp.). https://doi.org/10.1051/epjconf/202023907001
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Michalopoulou V, Stamatopoulos A, Vlastou R, Kokkoris M, Tsinganis A, Diakaki M, et al.
First results of the 230Th(n,f) cross section measurements at the CERN n_TOF facility
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Sine loco: EDP Science; 2020:05004 (6 pp.). https://doi.org/10.1051/epjconf/202023905004
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Mora DF, Niffenegger M, Mukin R
Crack propagation modeling in a PWR under PTS Using XFEM
In: Volume 6: materials and fabrication. Vol. 6. Pressure vessels and piping conference. New York, NY, USA: ASME; 2020:V006T06A001. https://doi.org/10.1115/PVP2020-21026
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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
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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
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Mylonakis AG, Demazière C, Vinai P, Lamirand V, Rais A, Pakari O, et al.
CORE SIM+ simulations of COLIBRI fuel rods oscillation experiments and comparison with measurements
In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1207 (9 pp.).
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Nakayoshi A, Rempe JL, Barrachin M, Bottomley D, Jacquemain D, Journeau C, et al.
Review of Fukushima Daiichi Nuclear Power Station debris endstate location in OECD/NEA preparatory study on analysis of fuel debris (PreADES) project
Nuclear Engineering and Design. 2020; 369: 110857 (15 pp.). https://doi.org/10.1016/j.nucengdes.2020.110857
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Nichenko S, Kalilainen J, Fernandez Moguel L, Lind T
Modelling of fission products release in VERDON-1 experiment with cGEMS: coupling of severe accident code MELCOR with GEMS thermodynamic modelling package
Annals of Nuclear Energy. 2020. https://doi.org/10.1016/j.anucene.2020.107972
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Oprea A, Gunsing F, Schillebeeckx P, Aberle O, Bacak M, Berthoumieux E, et al.
Neutron capture cross section measurements of 241Am at the n_TOF facility
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2020:01009 (5 pp.). https://doi.org/10.1051/epjconf/202023901009
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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
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Papadionysiou M, Kim S, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
Coupling of nTRACER to COBRA-TF for high-fidelity analysis of VVERs
In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1285 (8 pp.).
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Paranjape S, Kapulla R, Mignot G, Paladino D
Gas mixing caused by interacting heat sources PART I: experiments
Nuclear Engineering and Design. 2020; 370: 110914 (14 pp.). https://doi.org/10.1016/j.nucengdes.2020.110914
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Pellegrini M, Herranz L, Sonnenkalb M, Lind T, Maruyama Y, Gauntt R, et al.
Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF project
Nuclear Technology. 2020; 206(9): 1449-1463. https://doi.org/10.1080/00295450.2020.1724731
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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
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Perret G, Rochman D, Vasiliev A, Ferroukhi H
Neutron emission measurements of PWR spent fuel segments and preliminary validation of depletion calculations
In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1174 (10 pp.).
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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
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Pázsit I, Hursin M, Nylén H, Dykin V
Reconstructing the axial void velocity profile in BWRs from measurements of the in-core neutron noise
In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1337 (8 pp.).
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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
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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
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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
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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
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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
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Sakellarakis VD, Vera-Tudela W, Doll U, Ebi D, Wright YM, Boulouchos K
The effect of high-pressure injection variations on the mixing state of underexpanded methane jets
International Journal of Engine Research. 2020. https://doi.org/10.1177/1468087420960895
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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. 2020. https://doi.org/10.1016/j.net.2020.11.003
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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
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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.
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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
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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
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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
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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
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Sonnenkalb M, Pellegrini M, Herranz LE, Lind T, Morreale AC, Kanda K, et al.
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), phase 2 - results of severe accident analyses for unit 2
Nuclear Engineering and Design. 2020; 369: 110840 (10 pp.). https://doi.org/10.1016/j.nucengdes.2020.110840
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Soubelet B, Adams R, Kromer H, Prasser H-M
Calibration technique and sample measurement database for material decomposition imaging using a compact deuterium-deuterium (D-D) fast neutron generator
Radiation Physics and Chemistry. 2020; 176: 108930 (18 pp.). https://doi.org/10.1016/j.radphyschem.2020.108930
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Terranova N, Aberle O, Alcayne V, Amaducci S, Andrzejewski J, Audouin L, et al.
Monte Carlo simulations and n-p differential scattering data measured with Proton Recoil Telescopes
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2020:01024 (5 pp.). https://doi.org/10.1051/epjconf/202023901024
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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
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Vasiliev A, Pecchia M, Rochman D, Perret G, Ferroukhi H, Laureau A, et al.
Assessment of representativity of the PETALE experiments for validation of Swiss LWRs ex-core dosimetry calculations
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2020:22001 (6 pp.). https://doi.org/10.1051/epjconf/202023922001
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Vasiliev A, Pecchia M, Rochman D, Ferroukhi H
Enhancement of validation studies for reactor dosimetry and ativation predictions with the nuclear data sampling methodology
In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1427 (8 pp.).
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Vasiliev A, Pecchia M, Rochman D, Ferroukhi H, Alhassan E
On the impact of nuclear data uncertainties on LWR neutron dosimetry assessments
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2020:22003 (4 pp.). https://doi.org/10.1051/epjconf/202023922003
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Verma V, Chionis D, Dokhane A, Ferroukhi H
Modelling and analysis of fuel assembly vibrational modes in PWRs using SIMULATE-3K
In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1270 (8 pp.).
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
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Vitullo F, Krepel J, Kalilainen J, Prasser H-M, Pautz A
Statistical burnup distribution of moving pebbles in the HTR-PM reactor
Journal of Nuclear Engineering and Radiation Science. 2020; 6(2): 021108 (14 pp.). https://doi.org/10.1115/1.4044910
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Weilenmann M, Doll U, Bombach R, Blondé A, Ebi D, Xiong Y, et al.
Linear and nonlinear entropy-wave response of technically-premixed jet-flames-array and swirled flame to acoustic forcing
Proceedings of the Combustion Institute. 2020. https://doi.org/10.1016/j.proci.2020.06.233
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
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Alcayne V, Kimura A, Mendoza E, Cano-Ott D, Aberle O, Amaducci S, et al.
Measurement of the 244Cm and 246Cm neutron-induced cross sections at the n_TOF facility
In: García-Ramos J-E, Andrés MV, Pérez-Bernal F, Valera JA, Moro AM, eds. Basic concepts in nuclear physics: theory, experiments and applications. 2018 La Rábida international scientific meeting on nuclear physics. Vol. 225. Springer proceedings in physics. Cham: Springer; 2019:117-122. https://doi.org/10.1007/978-3-030-22204-8_4
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Andreani M, Paranjape S
Modelling of the interaction of two heat sources simulating the thermal effects of PARs
Presented at: ICAPP 2019 - International congress on advances in nuclear power plants; May 12-15, 2019; Juan-les-pins, France.
DORA PSI -
Andreani M, Gaikwad AJ, Ganju S, Gera B, Grigoryev S, Herranz LE, et al.
Synthesis of a CFD benchmark exercise based on a test in the PANDA facility addressing the stratification erosion by a vertical jet in presence of a flow obstruction
Nuclear Engineering and Design. 2019; 354: 110177 (31 pp.). https://doi.org/10.1016/j.nucengdes.2019.110177
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Babiano-Suarez V, Caballero L, Domingo-Pardo C, Ladarescu I, Aberle O, Alcayne V, et al.
Characterization and first test of an i-TED prototype at CERN n_TOF
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Chionis D, Dokhane A, Ferroukhi H, Pautz A
Application of causality analysis on nuclear reactor systems
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Chionis D, Dokhane A, Ferroukhi H, Pautz A
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Clifford I, Cozzo C, Ferroukhi H
First assessments of the dynamic gap conductance model in TRACE
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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
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Cozzo C, Ngayam-Happy R, Chen J-C, Pecchia M, Girardin G
Modeling of the U3Si2/SiC fuel system behavior for a RIA scenario
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Dehbi A, Kelm S, Kalilainen J, Mueller H
The influence of thermal radiation on the free convection inside enclosures
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Fernandez Moguel L, Lind T, Rýdl A
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Fernandez-Moguel L, Rydl A, Lind T
Updated analysis of Fukushima Unit 3 with MELCOR 2.1. Part 2: fission product release and transport analysis
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Fernandez-Moguel L, Rydl A, Lind T
Updated analysis of Fukushima unit 3 with MELCOR 2.1. Part 1: thermal-hydraulic analysis
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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: CFD modelling of the PPOOLEX and PANDA experiments
Nuclear Engineering and Design. 2019; 347: 67-85. https://doi.org/10.1016/j.nucengdes.2019.03.011
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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
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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
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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
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Herranz LE, Pellegrini M, Lind T, Sonnenkalb M, Godin-Jacqmin L, López C, et al.
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Hombourger B, Křepel J, Pautz A
Breed-and-burn fuel cycle in molten salt reactors
EPJ Nuclear Sciences and Technologies. 2019; 5: 15 (10 pp.). https://doi.org/10.1051/epjn/2019026
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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.
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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.
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Jäckel BS, Lind T, Fernandez-Moguel L, Steinbrück M, Park S
Application of a newly developed computer code model for nitriding and re-oxidation of cladding materials on separate effect tests and integral experiments
In: Proceedings of the ERMSAR 2019. sine loco: sine nomine; 2019:024 (14 pp.).
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Kalilainen J, Lind T, Stuckert J, Stegmaier U
Aerosol results of the QUENCH-18 bundle test
In: Proceedings of the ERMSAR 2019. sine loco: sine nomine; 2019:019 (11 pp.).
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Kalilainen J, Lind T, Stuckert J, Bergfeldt T, Sippula O, Jokiniemi J
The measurement of Ag/In/Cd release under air-ingress conditions in the QUENCH-18 bundle test
Journal of Nuclear Materials. 2019; 517: 315-327. https://doi.org/10.1016/j.jnucmat.2019.02.021
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Kapulla R, Paranjape S, Falsetti C, Paladino D
High spatial resolution PIV measurements in the PANDA facility
Presented at: ICAPP 2019 - international congress on advances in nuclear power plants; May 12-15, 2019; Juan-les-pins, France.
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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
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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
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Lamirand V, Laureau A, Rochman D, Perret G, Gruel A, Leconte P, et al.
An experimental programme optimized with uncertainty propagation: PETALE in the CROCUS reactor
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Laureau A, Lamirand V, Rochman D, Pautz A
Total Monte Carlo acceleration for the PETALE experimental programme in the CROCUS reactor
In: Serot O, Chebboubi A, eds. WONDER-2018 - 5th international workshop on nuclear data evaluation for reactor applications. Vol. 211. EPJ web of conferences. sine loco: EDP Sciences; 2019:03002 (5 pp.). https://doi.org/10.1051/epjconf/201921103002
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Lind T, Campbell S, Herranz LE, Kissane M, Song JH
A summary of fission-product-transport phenomena during SGTR severe accidents
In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park, IL, USA: American Nuclear Society (ANS); 2019:4063-4075.
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Lind T, Guentay S, Herranz LE, Suckow D
A summary of the ARTIST: aerosol retention during SGTR severe accident
Annals of Nuclear Energy. 2019; 131: 385-400. https://doi.org/10.1016/j.anucene.2019.04.006
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Lind T, Pellegrini M, Herranz LE, Sonnenkalb M, Nishi Y, Tamaki H, et al.
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Mala P, Pautz A, Ferroukhi H
EPR fuel cycle depletion with pin-by-pin code tortin and nodal code SIMULATE5
In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). La Grange Park, USA: American Nuclear Society; 2019:1640-1649.
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Massimi C, Aberle O, Alcayne V, Andrzejewski J, Audouin l., Bécares V, et al.
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Mora DF, Mukin R, Costa Garrido O, Niffenegger M
Fracture mechanics analysis of a PWR under PTS using XFEM and input from TRACE
In: Materials and fabrication: advanced and additive manufacturing and material technologies. Vol. 6A. PVP - American Society of Mechanical Engineers. Pressure vessels and piping division. sine loco: American Society of Mechanical Engineers (ASME); 2019:PVP2019-94019 (7 pp.). https://doi.org/10.1115/PVP2019-94019
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Mukin R, Clifford I, Costa Garrido O, Mora DF, Niffenegger M, Niceno B, et al.
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Niffenegger M, Garrido OC, Mora DF, Qian G, Mukin R, Sharabi M, et al.
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Nikitin K, Mueller P, Bruder A, Walser S, Judd J, Hiltbrand D
BWR-4 ATWS modeling with RELAP5-S3K
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Nikitin K, Clifford I, Ferroukhi H
PMSYS: plant management system as a part of Swiss Simulation Platform
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Papadionysiou M, Seongchan K, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
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In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). La Grange Park, USA: American Nuclear Society; 2019:700-709.
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Papadopoulos P, Tietze S, Suckow D, Ceder SJ, Roth B, Lind T
Hydrodynamic characterisation inside a wet scrubber for different flow regimes relevant for pool scrubbing and FCVS
In: Proceedings of the ERMSAR 2019. Prague: AF POWER agency; 2019:028 (10 pp.).
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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
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Paranjape S, Mignot G, Kapulla R, Paladino D
Experimental investigation of gas transport induced by containment spray activation during a scaled severe accident scenario
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Paranjape S, Kapulla R, Mignot G, Paladino D
Gas redistribution caused by interacting sources in the presence of a vertical condenser
Presented at: ICAPP 2019 - international congress on advances in nuclear power plants; May 12-15, 2019; Juan-les-pins, France.
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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
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Pecchia M, Vasiliev A, Perret G, Ferroukhi H
Benchmark Monte Carlo calculations with ENDF/B-VIII.0 and JEFF-3.3 libraries for LWR criticality safety assessments
Presented at: ICNC 2019 - 11th international conference on nuclear criticality safety; September 15-20, 2019; Paris, France.
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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
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Pelloni S, Rochman D
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Annals of Nuclear Energy. 2019; 129: 79-89. https://doi.org/10.1016/j.anucene.2019.01.057
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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
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Puragliesi R
Assessment of a URANS CFD model for gravity driven flows: a comparison with OECD/PKL2 ROCOM experiments
Nuclear Engineering and Design. 2019. https://doi.org/10.1016/j.nucengdes.2019.110365
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Puragliesi R, Mukin R, Clifford I, Ferroukhi H, Seidl M
Comparison of computational fluid dynamics and subchannel numerical solutions of fuel assemblies characterized by bowing
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Rais A, Lamirand V, Pakari O, Laureau A, Pohlus J, Pohl C, et al.
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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
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Scolaro A, Clifford I, Fiorina C, Pautz A
Cladding plasticity modeling with the multidimensional fuel performance code OFFBEAT
In: Global/top fuel 2019. LaGrange Park, IL, USA: American Nuclear Society (ANS); 2019:47-55.
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Scolaro A, Robert Y, Fiorina C, Clifford I, Pautz A
Coupling methodology for the multidimensional fuel performance code OFFBEAT and the Monte Carlo neutron transport code Serpent
In: Global/top fuel 2019. LaGrange Park, IL, USA: American Nuclear Society (ANS); 2019:1174-1183.
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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
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Siefman D, Hursin M, Pautz A
Data assimilation of post irradiation examination experiments to adjust fission yields
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Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes – PREMIUM benchmark
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Sonnenkalb M, Pellegrini M, Herranz LE, Lind T, Morreale AC, Kanda K, et al.
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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
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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
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Tagliente G, Aberle O, Alcayne V, Andrzejewski J, Audouin L, Babiano-Suarez V, et al.
Nuclear astrophysics at n_TOF facility, CERN
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Tassan-Got L, Colonna N, Diakaki M, Eleme Z, Manna A, Sekhar A, et al.
Fission program at n_TOF
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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
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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
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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
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Verma V, Demazière C, Vinai P, Ricciardi G, Jacqmin R
Assessment of the neutron noise induced by stationary fuel assembly vibrations in a light water reactor
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Wolfertz A, Adams R, Perret G
First tests of a gamma-blind fast neutron detector prototype based on ZnS and wavelength-shifting fibers
Presented at: ANS annual meeting 2019. The value of nuclear; June 9-13, 2019; Minneapolis, USA.
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Yang J, Suckow D, Lind T, Prasser H-M
Study of level swell for a Filtered Containment Venting System at the VEFITA facility
Progress in Nuclear Energy. 2019; 113: 7-17. https://doi.org/10.1016/j.pnucene.2019.01.003
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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
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Andreani M, Kapulla R
Analyses of gas stratification erosion by a vertical jet in presence of an obstacle using the GOTHIC code
In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. Vol. 6B. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-82360 (11 pp.). https://doi.org/10.1115/ICONE26-82360
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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
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Bates E, Zhang D, Truong B, Sui D, Hu W, Su GH, et al.
Conclusions of a benchmark study on the EBR-II SHRT-45R experiment
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IAEA's coordinated research project on EBR-II shutdown heat removal tests: an overview
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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
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Beghi I, Tietze S, Lind T, Prasser H-M
Effect of hydrodynamics on the retention of iodine in a wet scrubber
In: International congress on advances in nuclear power plants (ICAPP 2018). Vol. 1. Illinois: American Nuclear Society; 2018:302-309.
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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
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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
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Briggs L, Kriventsev V, Monti S, Hu W, Sui D, Su G, et al.
Benchmark analyses of EBR-II shutdown heat removal tests
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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
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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)
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Chionis D, Dokhane A, Ferroukhi H, Girardin G, Pautz A
PWR neutron noise phenomenology: part I - simulation of stochastic phenomena with simulate-3K
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Chionis D, Dokhane A, Ferroukhi H, Girardin G, Pautz A
PWR neutron noise phenomenology: part II - qualitative comparison against plant data
In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018:1013-1024.
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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
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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
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Cozzo C, Khvostov G
ATF developments in FALCON V1 at PSI
In: Topfuel 2018. Part 4. Brussels: European Nuclear Society; 2018:A0112 (9 pp.).
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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
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De Sousa Ribeiro F, Calivá F, Chionis D, Dokhane A, Mylonakis A, Demazière C, et al.
Towards a deep unified framework for nuclear reactor perturbation analysis
In: Sundaram S, ed. Proceedings of the 2018 IEEE symposium series on computational intelligence (SSCI 2018). Piscataway: IEEE; 2018:120-127. https://doi.org/10.1109/SSCI.2018.8628637
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Dokhane A, Vasiliev A, Rochman D, Ferroukhi H, Grandi G
Analyses of the SPERT-III RIA experiments with nuclear data uncertainty quantification using three different covariance matrix libraries
In: Proceedings of the PHYTRA4 conference. sine loco: American Nuclear Society (ANS); 2018:91-102.
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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
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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
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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
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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
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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
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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
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Griffin PJ, Koning A, Rochman D
Importance of treating correlations in the uncertainty quantification of radiation damage metrics
In: Radiation protection and shielding division 20th topical meeting. Illinois: American Nuclear Society (ANS); 2018:(10 pp.).
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Hombourger B, Krepel J, Mikityuk K, Pautz A
On the feasibility of Breed-and-Burn fuel cycles in Molten Salt Reactors
In: Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vol. CN245. Proceedings series (International Atomic Energy Agency). Vienna: International Atomic Energy Agency; 2018:388 (11 pp.).
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Hursin M, Siefman D, Perret G, Rochman D, Vasiliev A, Ferroukhi H
Determination of sobol sensitivity indices for correlated inputs with SHARK-X
In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018:(12 pp.).
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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
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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
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Jäckel BS, Lind T, Fernandez-Moguel L, Steinbrück M, Park S
Development of a computer code model for nitriding and re‐oxidation of cladding materials under severe accident conditions
In: Proceedings of the international conference nuclear energy for New Europe (NENE 2018). Ljubljana: Nuclear Society of Slovenia; 2018:506.1 (8 pp.).
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Kalilainen J, Kim H, Dehbi A, Lind T
Aerosol depletion in natural circulation in simplified geometry
In: International congress on advances in nuclear power plants (ICAPP 2018). Vol. 1. Illinois: American Nuclear Society; 2018:571-577.
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Kalilainen J, Lind T, Prasser H-M
Loss of forced cooling accident analysis of HTR-PM using MELCOR 2.2 code
In: Proceedings of HTR 2018. sine loco: sine nomine; 2018:(7 pp.).
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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
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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
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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
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Krepel J
Comparison of fast reactors performance in the closed U-Pu and Th-U cycle
In: Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vol. CN245. Proceedings series (International Atomic Energy Agency). Vienna: International Atomic Energy Agency; 2018:052 (10 pp.).
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Kromer H, Adams R, Soubelet B, Zboray R, Prasser HM
Improvement of a compact fast neutron generator for imaging applications
In: 2018 IEEE nuclear science symposium and medical imaging conference proceedings (NSS/MIC). sine loco: IEEE; 2018:(3 pp.). https://doi.org/10.1109/NSSMIC.2018.8824470
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Lamirand V, Perret G, Radman S, Siefman D, Frajtag P, Hursin M, et al.
Design of separated element reflector experiments in CROCUS: PETALE
In: Sparks MH, DePriest KR, Vehar DW, eds. Reactor dosimetry: 16th international symposium. West Conshohocken, USA: ASTM International; 2018:1-14. https://doi.org/10.1520/STP160820170090
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Lamirand V, De Izzarra G, Krasa A, Perret G, Pakari O, Frajtag P, et al.
Intercomparison of neutron noise measurement systems in the CROCUS reactor
In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018:(11 pp.).
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Mambelli S, Mikityuk K, Panadero A-L
Chugging boiling in low-void SFR core: new phenomenology of unprotected loss of flow
In: Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vol. CN245. Proceedings series (International Atomic Energy Agency). Vienna: International Atomic Energy Agency; 2018:451 (9 pp.).
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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
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Mikityuk K, Girardi E, Krepel J, Bubelis E, Fridman E, Rineiski A, et al.
ESFR-SMART: new Horizon-2020 project on SFR safety
In: Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vol. CN245. Proceedings series (International Atomic Energy Agency). Vienna: International Atomic Energy Agency; 2018:450 (10 pp.).
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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
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Mukin R, Clifford I, Ferroukhi H, Niffenegger M
Pressurized Thermal Shock (PTS) transient scenarios analysis with TRACE
In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-81749 (7 pp.). https://doi.org/10.1115/ICONE26-81749
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Mukin R, Seidl M, Clifford I, Ferroukhi H
Sensitivity of CTF solution to subchannel window size
In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-82546 (11 pp.). https://doi.org/10.1115/ICONE26-82546
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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
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Ngayam-Happy R, Cozzo C, Khvostov G, Krack M, Ferroukhi H
Fuel thermo-mechanical simulations with uncertainty quantification and sensitivity analysis of the OECD/NEA RIA code benchmark using FALCON and URANIE
Presented at: ANS Best estimate plus uncertainty International conference (BEPU 2018); May 13-18, 2018; Lucca, Italy.
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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
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Pakari O, Lamirand V, Perret G, Braun L, Frajtag P, Pautz A
Current mode neutron noise measurements in the zero power reactor CROCUS
In: Lyoussi A, Carette M, Giot M, Le Dû P, Reynard-Carette C, Schyns M, et al., eds. ANIMMA 2017 - advancements in nuclear instrumentation measurement methods and their applications. Vol. 170. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2018:04017 (5 pp.). https://doi.org/10.1051/epjconf/201817004017
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Pakari O, Lamirand V, Perret G, Godat D, Hursin M, Frajtag P, et al.
Investigation of spatial effects on neutron noise measurements in the zero power reactor CROCUS
In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018:(12 pp.).
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