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Dieser Inhalt ist nicht auf Deutsch verfügbar.Journal Publications 2020
2020
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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
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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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Fiorina C, Scolaro A, Siefman D, Hursin M, Pautz A
Artificial neural networks as surrogate models for uncertainty quantification and data assimilation in 2-D/3-D fuel performance studies
Journal of Nuclear Engineering. 2020; 1(1): 54-62. https://doi.org/10.3390/jne1010005
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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
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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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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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Konarski P, Cozzo C, Khvostov G, Ferroukhi H
Dry storage modeling activities at PSI: implementation and testing of a creep model for dry storage
Kerntechnik. 2020; 85(6): 419-425. https://doi.org/10.3139/124.200072
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Laureau A, Lamirand V, Rochman D, Pautz A
Uncertainty propagation based on correlated sampling technique for nuclear data applications
EPJ Nuclear Sciences and Technologies. 2020; 6: 8 (9 pp.). https://doi.org/10.1051/epjn/2020003
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Laureau A, Lamirand V, Rochman D, Pautz A
Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor
EPJ Nuclear Sciences and Technologies. 2020; 6: 9 (8 pp.). https://doi.org/10.1051/epjn/2020004
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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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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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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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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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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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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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Puragliesi R
Assessment of a URANS CFD model for gravity driven flows: a comparison with OECD/PKL2 ROCOM experiments
Nuclear Engineering and Design. 2020; 356: 110365 (13 pp.). https://doi.org/10.1016/j.nucengdes.2019.110365
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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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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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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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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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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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