Conference Publications of the STARS Program

2022

  • Al-Yahia OS, Clifford I, Nikitin K, Ferroukhi H
    Parametric study on the modeling of the open passive containment cooling system (CWC)
    Presented at: The 13th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-13); September 5-10, 2022; Hsinchu.
    DORA PSI
  • Babiano-Suarez V, Balibrea-Correa J, Caballero-Ontanaya L, Domingo-Pardo C, Ladarescu I, Lerendegui-Marco J, et al.
    First 80Se(n,γ) cross section measurement with high resolution in the full stellar energy range 1 eV - 100 keV and its astrophysical implications for the s-process
    In: Liu W, Wang Y, Guo B, Tang X, Zeng S, eds. Symposium on nuclei in the cosmos. 16th symposium on nuclei in the cosmos, NIC-XVI 2021. Les Ulis Cedex A: EDP Sciences; 2022:11026 (8 pp.). https://doi.org/10.1051/epjconf/202226011026
    DORA PSI
  • D'Ambrosi V, Sercombe J, Beajoui S, Chaieb A, Baurens B, Largenton R, et al.
    P2M simulation exercise on past fuel melting irradiation experiments: main outcomes on fuel melting assessment in PWR fuel
    In: TopFuel 2022 light water reactor fuel performance conference. Illinois: American Nuclear Society; 2022:344-353. https://doi.org/10.13182/TopFuel22-38827
    DORA PSI
  • Diomidis N, Pudollek S, Wittel M, Frankl M, Vasiliev A
    Post-closure canister degradation scenarios in deep geological disposal: preliminary definition and evaluation of potential impact on reactivity
    In: Nuclear Criticality Safety division topical meeting (NCSD 2022). La Grange Park: American Nuclear Society; 2022:(7 pp.). https://www.ans.org/pubs/proceedings/article-51979/.
    DORA PSI
  • Fogliatto E, Clifford I, Ferroukhi H, Puragliesi R
    The influence of scaling on turbulent mixing in reactor pressure vessels and core-inlet flow distribution
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35578 (14 pp.).
    DORA PSI
  • Hursin M, Mala P, Vasiliev A, Ferroukhi H, Liu Y, Choi S, et al.
    Comparison of CASMO-5, MPACT and Serpent 2 for the modeling of advanced BWR lattices
    In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:2762-2772.
    DORA PSI
  • Hursin M, Mala P, Vasiliev A, Ferroukhi H, Liu Y, Choi S, et al.
    Comparison of CASMO-5, MPACT and Serpent 2 for the modeling of advanced BWR lattices
    In: International conference on physics of reactors. Proceedings of the international conference on physics of reactors, PHYSOR 2022. Downers Grove: American Nuclear Society; 2022:2762-2772. https://doi.org/10.13182/PHYSOR22-37760
    DORA PSI
  • Hursin M, Cabelloas O, Palmiotti G
    Status of the WPEC subgroup 46 efficient and effective use of integral experiments for nuclear data validation
    In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:1095-1104. https://doi.org/10.13182/PHYSOR22-37758
    DORA PSI
  • Lee H, Vasiliev A, Ferroukhi H
    Verification of legacy methodology of minimum critical mass estimation at PSI
    Presented at: GLOBAL 2022 - sustainable energy beyond the pandemic; July 6-8, 2022; Reims.
    DORA PSI
  • Mager T, Hursin M, Fiorina C, Pautz A
    Development of a high fidelity model of the CROCUS experimental reactor
    In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:946-956. https://doi.org/10.13182/PHYSOR22-37250
    DORA PSI
  • Martin J-F, Ivanova T, Bess J, Carmouze C, Gan S, Wilson AR, et al.
    The OECD NEA working party on nuclear criticality safety. Recent outcome, work in progress and outlook
    In: Nuclear Criticality Safety division topical meeting (NCSD 2022). La Grange Park: American Nuclear Society; 2022:(10 pp.). https://www.ans.org/pubs/proceedings/article-51992/.
    DORA PSI
  • Nikitin K, Arnold B, Clifford I, Ferroukhi H
    CPR estimation by CTF subchannel code with machine learning support
    Presented at: The 13th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-13); September5-10, 2022; Hsinchu.
    DORA PSI
  • Papadionysiou M, Seongchan K, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
    Coupling of COBRA-TF to nTRACER for full core high fidelity analysis of VVERs
    In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:586-595.
    DORA PSI
  • Papadionysiou M, Seongchan K, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
    Coupling of nTRACER to COBRA-TF for full core high-fidelity analysis of VVERs
    In: International conference on physics of reactors. Proceedings of the international conference on physics of reactors, PHYSOR 2022. Downers Grove: American Nuclear Society; 2022:586-595. https://doi.org/10.13182/PHYSOR22-37390
    DORA PSI
  • Perret G, Clifford I, Ferroukhi H
    Bias and uncertainty considerations for trace predictions of RBHT reflood experiments
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:19001 (14 pp.).
    DORA PSI
  • Raffuzzi V, Sublet JC, Jouanne C, Koning A, Rochman D
    An iron evaluation story: from TALYS model parameters to validation on the ASPIS benchmark with the Monte Carlo code TRIPOLI-4®
    In: International conference on physics of reactors. Proceedings of the international conference on physics of reactors, PHYSOR 2022. Downers Grove: American Nuclear Society; 2022:1361-1370. https://doi.org/10.13182/PHYSOR22-37310
    DORA PSI
  • Raffuzzi V, Sublet J-C, Jouanne C, Koning A, Rochman D
    An iron evaluation story: from TALYS model parameters to validation on the ASPIS benchmark with the Monte Carlo code TRIPOLI-4®
    In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:1361-1370.
    DORA PSI
  • Scolaro A, Fiorina C, Siefman D, Hursin M, Pautz A
    Bayesian data assimilation for fuel performance based on OFFBEAT
    In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:3656-3665. https://doi.org/10.13182/PHYSOR22-37357
    DORA PSI
  • Scolaro A, Fiorina C, Clifford I, Brunetto E, Pautz A
    Pre-release validation database for the multi-dimensional fuel performance code OFFBEAT
    In: International conference on physics of reactors. Proceedings of the international conference on physics of reactors, PHYSOR 2022. Downers Grove: American Nuclear Society; 2022:2914-2923. https://doi.org/10.13182/PHYSOR22-37789
    DORA PSI
  • Sublet JC, Koning A, Rochman D, Gilbert MR, Kahler AC, Jouanne C, et al.
    Multifaceted coded nuclear data libraries assemblage, verification and validation: TENDL-2021
    In: International conference on radiation shielding and topical meeting of the radiation protection and shielding division. Proceedings of the 14th international conference on radiation shielding and 21st topical meeting of the radiation protection and shielding division, ICRS 2022/RPSD 2022. American Nuclear Society; 2022:308-311. https://doi.org/10.13182/ICRSRPSD22-39025
    DORA PSI
  • Zahur A, Park J, Cherezov A, Jo Y, Lee D
    Reactivity initiated accident uncertainty quantification for fuel assembly with subchannel code
    In: International conference on physics of reactors. Proceedings of the international conference on physics of reactors, PHYSOR 2022. Downers Grove: American Nuclear Society; 2022:1667-1676. https://doi.org/10.13182/PHYSOR22-37528
    DORA PSI

2021

  • Bernal A, Pecchia M, Rochman D, Vasiliev A, Ferroukhi H
    Methodology for high-fidelity deterministic modelling of Swiss LWR fuel assemblies
    In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:06011 (8 pp.). https://doi.org/10.1051/epjconf/202124706011
    DORA PSI
  • Cozzo C, Allagbe C, Alonso JR, Ben Ouaghrem K, Cizelj L, Degueldre D, et al.
    EUROSAFE: fostering the sharing of nuclear expertise
    In: Vázquez-Rodriguez C, Jiménez Carrascosa A, Estevez Albuja S, Duran Vinuesa LF, eds. Book of Proceedings. European nuclear young generation forum 2021. sine loco: European Nuclear Young Generation Forum; 2021:623-626.
    DORA PSI
  • Cozzo C, Lind T, Bertsch J, Nichenko S, Girardin G
    Quantifying the benefits of the reduced oxidation kinetics in chromium-coated cladding: a parametric study
    In: Vázquez-Rodriguez C, Jiménez Carrascosa A, Estevez Albuja S, Duran Vinuesa LF, eds. Book of Proceedings. European nuclear young generation forum 2021. sine loco: European Nuclear Young Generation Forum; 2021:245-248.
    DORA PSI
  • Fiorina C, Shriwise P, Dufresne A, Ragusa J, Ivanov K, Valentine T, et al.
    An initiative for the development and application of open-source multi-physics simulation in support of R&D and E&T in Nuclear Science and Technology
    In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:02040 (7 pp.). https://doi.org/10.1051/epjconf/202124702040
    DORA PSI
  • 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: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:09005 (10 pp.). https://doi.org/10.1051/epjconf/202124709005
    DORA PSI
  • Hursin M, Vasiliev A, Rochman D, Dokhane A, Ferroukhi H
    Monte Carlo analysis of sub-pin resolved power behaviour in modern BWR assembly designs
    In: Proceedings of the international conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2021). Illinois: American Nuclear Society (ANS); 2021:758-767. https://doi.org/10.13182/M&C21-33772
    DORA PSI
  • 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: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:08004 (8 pp.). https://doi.org/10.1051/epjconf/202124708004
    DORA PSI
  • Konarski P, Cozzo C, Khostov G, Ferroukhi H
    Extension of Falcon's modelling capabilities to dry storage: development of a new model for hydrogen behavior in duplex claddings
    In: TopFuel2021. Brussels: European Nuclear Society; 2021:(10 pp.).
    DORA PSI
  • Lamirand V, Rais A, Pakari O, Hursin M, Laureau A, Pohlus J, et al.
    Analysis of the first COLIBRI fuel rods oscillation campaign in the CROCUS reactor for the European project CORTEX
    In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:21010 (9 pp.). https://doi.org/10.1051/epjconf/202124721010
    DORA PSI
  • Mager T, Fiorina C, Hursin M, Pautz A
    Validation of the gen-foam model of the crocus experimental reactor
    In: Proceedings of the international conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2021). Illinois: American Nuclear Society (ANS); 2021:738-747. https://doi.org/10.13182/M&C21-33754
    DORA PSI
  • Mala P, Pautz A, Ferroukhi H, Vasiliev A
    Development of 3D pin-by-pin core solver tortin and coupling with thermal-hydraulics
    In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:02034 (8 pp.). https://doi.org/10.1051/epjconf/202124702034
    DORA PSI
  • 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: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:21006 (9 pp.). https://doi.org/10.1051/epjconf/202124721006
    DORA PSI
  • Papadionysiou M, Seongchan K, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
    Coupling of nTRACER to COBRA-TF for high-fidelity analysis of VVERs
    In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:02008 (8 pp.). https://doi.org/10.1051/epjconf/202124702008
    DORA PSI
  • Papadionysiou M, Kim S, Hursin M, Vasiliev A, Ferroukhi H, Joo HG, et al.
    Validation of the high-resolution code nTRACER against VVER-1000 hot zero power measurements
    In: Proceedings of the international conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2021). Illinois: American Nuclear Society (ANS); 2021:700-709. https://doi.org/10.13182/M&C21-33678
    DORA PSI
  • Perret G, Rochman D, Vasiliev A, Ferroukhi H
    Neutron emission measurements of PWR spent fuel segments and preliminary validation of depletion calculations
    In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:10004 (10 pp.). https://doi.org/10.1051/epjconf/202124710004
    DORA PSI
  • 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: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:02013 (8 pp.). https://doi.org/10.1051/epjconf/202124702013
    DORA PSI
  • Scolaro A, Fiorina C, Van Uffelen P, Schubert A, Clifford I, Pautz A
    Coupling methodology between TRANSURANUS and the multi-dimensional fuel performance code OFFBEAT
    In: Proceedings 2021 ANS winter meeting. Vol. 125. Transactions of the American Nuclear Society. American Nuclear Society; 2021:520-523. https://doi.org/10.13182/T125-36688
    DORA PSI
  • Szabolcs Ványi A, Hursin M, Czifrus S
    Investigation of recently introduced diffusion coefficient generation methods
    In: Cizelj L, Tekavčič M, eds. NENE2021 conference proceedings. Ljubljana: Nuclear Society of Slovenia; 2021:311 (8 pp.).
    DORA PSI
  • Tasakos T, Ioannou G, Verma V, Alexandridis G, Dokhane A, Stafylopatis A
    Deep learning-based anomaly detection in nuclear reactor cores
    In: Tasakos T, Ioannou G, Verma V, Alexandridis G, Dokhane A, Stafylopatis A, eds. Proceedings of the international conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2021). Illinois: American Nuclear Society (ANS); 2021:2026-2037. https://doi.org/10.13182/M&C21-33681
    DORA PSI
  • Torres LA, Chionis D, Montalvo C, Dokhane A, García-Berrocal A
    Neutron noise spectral features of simulated mechanical and thermal-hydraulic perturbations in a PWR core
    In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:21001 (8 pp.). https://doi.org/10.1051/epjconf/202124721001
    DORA PSI
  • Valentine T, Avramova M, Fleming M, Hursin M, Ivanov K, Petruzzi A, et al.
    Overview of the OECD-NEA expert group on multi-physics experimental data, benchmarks and validation
    In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:06048 (8 pp.). https://doi.org/10.1051/epjconf/202124706048
    DORA PSI
  • Vasiliev A, Pecchia M, Rochman D, Ferroukhi H
    Enhancement of validation studies for reactor dosimetry and activation predictions with the nuclear data sampling methodology
    In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:10021 (8 pp.). https://doi.org/10.1051/epjconf/202124710021
    DORA PSI
  • Verma V, Chionis D, Dokhane A, Ferroukhi H
    Modelling and analysis of fuel assembly vibrational modes in PWRs using SIMULATE-3K
    In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:21008 (8 pp.). https://doi.org/10.1051/epjconf/202124721008
    DORA PSI

2020

  • Rochman D
    Building bridges between nuclear reactions and statistical models
    In: Dimitriou P, Capote R, Schnabel G, eds. International workshop on compound-nuclear reactions and related topics. Vol. 322. EPJ web of conferences. Les Ulis: EDP Sciences; 2025:01003 (3 pp.). https://doi.org/10.1051/epjconf/202532201003
    DORA PSI
  • Albà A, Adelmann A, Rochman D
    Uncertainty quantification on spent nuclear fuel with LMC
    In: Suyama K, Gunji S, Watanabe T, Araki S, Fukuda K, Shimada K, et al., eds. Proceedings of the 12th international conference on nuclear criticality safety. Japan Atomic Energy Agency; 2024:1-10.
    DORA PSI
  • Berry L, Vasiliev A, Rochman D, Hursin M, Frankl M, Ferroukhi H
    Upgrading the neutronic version of the PSI cycle check-up methodology for full core PWR Monte Carlo simulations
    In: Zoia A, Diop CM, Saikali E, eds. Joint international conference on supercomputing in nuclear applications + Monte Carlo (SNA + MC 2024). Vol. 302. EPJ Web of Conferences. Les Ulis Cedex A: EDP Sciences; 2024:13004 (10 pp.). https://doi.org/10.1051/epjconf/202430213004
    DORA PSI
  • Berry L, Vasiliev A, Hursin M, Rochman D, Frankl M, Ferroukhi H
    Verification and validation of Monte Carlo simulations using Swiss PWR HZP data
    In: Suyama K, Gunji S, Watanabe T, Araki S, Fukuda K, Shimada K, et al., eds. Proceedings of the 12th international conference on nuclear criticality safety. Japan Atomic Energy Agency; 2024:1-10.
    DORA PSI
  • Biot G, Rochman D, Ducru P, Forget B
    Evaluating embedded Monte Carlo vs. total Monte Carlo for nuclear data uncertainty quantification
    In: Zoia A, Diop CM, Saikali E, eds. Joint international conference on supercomputing in nuclear applications + Monte Carlo (SNA + MC 2024). Vol. 302. EPJ Web of Conferences. Les Ulis Cedex A: EDP Sciences; 2024:07016 (13 pp.). https://doi.org/10.1051/epjconf/202430207016
    DORA PSI
  • Carmouze C, Ichou R, Ilas G, Alvarez-Velarde F, Chernykh M, García-Baonza R, et al.
    Overview of spent nuclear fuel inventory results for the ARIANE GU3 sample
    In: Suyama K, Gunji S, Watanabe T, Araki S, Fukuda K, Shimada K, et al., eds. Proceedings of the 12th international conference on nuclear criticality safety. Japan Atomic Energy Agency; 2024:1-10.
    DORA PSI
  • Cozzo C, Berti N
    Perfomance assessment of SiC cladding with cracking threshold in Falcon
    In: Proceedings of TopFuel 2024 reactor fuel performance conference. European Nuclear Society (ENS); 2024:(10 pp.).
    DORA PSI
  • Frankl M, Vasiliev A, Berry L, Rochman D, Ferroukhi H, Diomidis N, et al.
    Investigation of the specific keff behaviour in simplified corrosion scenarios for a potential PWR final disposal canister design
    In: Suyama K, Gunji S, Watanabe T, Araki S, Fukuda K, Shimada K, et al., eds. Proceedings of the 12th international conference on nuclear criticality safety. Japan Atomic Energy Agency; 2024:1-7.
    DORA PSI
  • Frankl M, Vasiliev A, Rochman D, Ferroukhi H, Wittel M, Pudollek S
    Refinement of the loading curve determination methodology and modeling for Swiss PWR spent fuel final disposal canisters
    In: Suyama K, Gunji S, Watanabe T, Araki S, Fukuda K, Shimada K, et al., eds. Proceedings of the 12th international conference on nuclear criticality safety. Japan Atomic Energy Agency; 2024:1-10.
    DORA PSI
  • Hoefer A, Stuke M, Abdel-Khalik HS, Cabellos O, Chernykh M, Eisenstecken T, et al.
    Bias and correlated data, comparison of methods
    In: Suyama K, Gunji S, Watanabe T, Araki S, Fukuda K, Shimada K, et al., eds. Proceedings of the 12th international conference on nuclear criticality safety. Japan Atomic Energy Agency; 2024:1-10.
    DORA PSI
  • Maccario S, Scolaro A, Vasiliev A, Hursin M
    Comparison of Bayesian model calibration techniques for future application to fuel performance behavior models
    In: Proceedings of the international conference on physics of reactors (PHYSOR 2024). La Grange Park: American Nuclear Society; 2024:551-560. https://doi.org/10.13182/PHYSOR24-43853
    DORA PSI
  • Martin J-F, Vasiliev A, O’Connor G, Ivanova T
    The NEA’s working party on nuclear criticality safety: tackling global challenges through international cooperation
    In: Suyama K, Gunji S, Watanabe T, Araki S, Fukuda K, Shimada K, et al., eds. Proceedings of the 12th international conference on nuclear criticality safety. Japan Atomic Energy Agency; 2024:1-10.
    DORA PSI
  • Monleón de la Lluvia JA, Brovchenko M, Rochman D, Dumonteil E
    Sensitivity analysis and uncertainty quantification in PWR irradiation ageing like problems
    In: Proceedings of the radiation protection and shielding division (RPSD 2024). Illinois: American Nuclear Society; 2024:224-228. https://doi.org/10.13182/T131-45734
    DORA PSI
  • Nikitin K, Arnold B, Clifford I, Ferroukhi H
    Critical Power Ratio (CPR) calculation methods for BWR licensing support
    In: Proceedings of SCOPE. ; 2024:23222 (8 pp.).
    DORA PSI
  • Papadionysiou M, Albagami T, Delipei G, Avramova M, Vasiliev A, Ferroukhi H, et al.
    Multi-physics sub-pin resolution analysis of a PWR core with nTRACER/CTF for the OECD/NEA TVA watts bar 1 benchmark
    In: Proceedings of the international conference on physics of reactors (PHYSOR 2024). La Grange Park: American Nuclear Society; 2024:1968-1977. https://doi.org/10.13182/PHYSOR24-43543
    DORA PSI
  • Pérez-Maroto P, Guerrero C, Casanovas A, Fernández B, Aberle O, Alcayne V, et al.
    Description and outlook of the 50,53Cr(n,γ) cross section measurement at n_TOF and HiSPANoS
    In: Serot O, Chebboubi A, eds. WONDER-2023 - 6th international workshop on nuclear data evaluation for reactor applications. Vol. 294. EPJ Web of Conferences. Les Ulis Cedex A: EDP Sciences; 2024:01004 (7 pp.). https://doi.org/10.1051/epjconf/202429401004
    DORA PSI
  • Rochman D, Algora A, Bremnes Ø, Cabellos O, Caruso S, Fiorito L, et al.
    Decay heat of irradiated nuclear fuels – a status report from the NEA WPNCS
    In: Suyama K, Gunji S, Watanabe T, Araki S, Fukuda K, Shimada K, et al., eds. Proceedings of the 12th international conference on nuclear criticality safety. Japan Atomic Energy Agency; 2024:1-10.
    DORA PSI
  • Rochman D, Koning AJ, van der Marck SC
    The TENDL nuclear data library: for criticality calculations and more
    In: Suyama K, Gunji S, Watanabe T, Araki S, Fukuda K, Shimada K, et al., eds. Proceedings of the 12th international conference on nuclear criticality safety. Japan Atomic Energy Agency; 2024:1-8.
    DORA PSI
  • Sanchez-Caballero A, Alcayne V, Andrzejewski J, Cano-Ott D, Cardinaels T, Dries P, et al.
    Experimental setup of the 239Pu neutron capture and fission cross-section measurements at n_TOF, CERN
    In: Serot O, Chebboubi A, eds. International workshop on nuclear data evaluation for reactor applications. Vol. 294. EPJ Web of Conferences. Les Ulis: EDP Sciences; 2024:01003 (9 pp.). https://doi.org/10.1051/epjconf/202429401003
    DORA PSI
  • Shama A, Wittel M, Rochman D
    Depletion and criticality analsyses - Case study of burnup credit of a PWR disposal canister
    In: Proceedings of TopFuel 2024 reactor fuel performance conference. European Nuclear Society (ENS); 2024:121-129.
    DORA PSI
  • Tagliente G, Aberle O, Alcayne V, Amaducci S, Andrzejewski J, Babiano-Suarez V, et al.
    The n_TOF facility at CERN
    In: Cerutti F, Kawano T, Marin S, Pujol F, Talou P, eds. 16th Varenna conference on nuclear reaction mechanisms (NRM2023). Vol. 292. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2024:12002 (8 pp.). https://doi.org/10.1051/epjconf/202429212002
    DORA PSI
  • Tagliente G, Aberle O, Alcayne V, Amaducci S, Andrzejewski J, Babiano-Suarez V, et al.
    The n_TOF facility at CERN
    In: Pizzone RG, Guardo GL, La Cognata M, Prajapati PM, Suryanarayana SV, Sivarani T, eds. International symposium on nuclear astrophysics (ISNA23). Vol. 297. EPJ Web of Conferences. Les Ulis Cedex A: EDP Sciences; 2024:01013 (8 pp.). https://doi.org/10.1051/epjconf/202429701013
    DORA PSI
  • Vasiliev A, Lee H, Frankl M, Hursin M, Ferroukhi H
    On the PSI routine criticality safety evaluation methodology and its validation approach
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  • Vasiliev A, Ferroukhi H, Pecchia M, Rochman D, Laureau A, Lamirand V, et al.
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  • Vasiliev A, Frankl M, Rochman D, Wittel M, Hoefer A
    Towards a direct comparison of practical CSE with BUC approaches: benchmark for a pseudo-application case with user-defined NCS criteria
    In: Suyama K, Gunji S, Watanabe T, Araki S, Fukuda K, Shimada K, et al., eds. Proceedings of the 12th international conference on nuclear criticality safety. Japan Atomic Energy Agency; 2024:1-8.
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  • Verma L, Clifford I, Ferroukhi H, Scolaro A
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  • Al-Yahia OS, Bernard M, Clifford I, Perret G, Bajorek S, Ferroukhi H
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  • Cabellos O, Hursin M, Palmiotti P
    WPEC/SG46 exercise on target accuracy requirement
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  • Clifford I, Al-Yahia OS, Ferroukhi H
    TRACE investigation on the performance of passive safety condenser as ultimate heat sink
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  • Domingo-Pardo C, Babiano-Suarez V, Balibrea-Correa J, Caballero L, Ladarescu I, Lerendegui-Marco J, et al.
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  • Fogliatto E, Clifford I
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  • Mucciola R, Paradela C, Manna A, Alaerts G, Massimi C, Kopecky S, et al.
    Neutron capture and total cross-section measurements on 94,95,96 Mo at n_TOF and GELINA
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  • Nikitin K, Arnold B, Clifford I, Ferroukhi H
    Application of CTF subchannel code for BWR reload licensing analysis support
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  • Oprea A, Gunsing F, Schillebeeckx P, Aberle O, Bacak M, Berthoumieux E, et al.
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    Detector set up for the measurements of the neutron-induced fission cross section of 235U relative to n-p scattering up to 150 MeV at CERN-n_TOF
    In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:01043 (5 pp.). https://doi.org/10.1051/epjconf/202328404019
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  • Puustinen M, Patel G, Kral P, Nikl T, Clifford I, Trewin R, et al.
    LTO modifications to reduce the pts issue - results of TH calculations in the context of the APAL European project
    In: Proceedings 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:282-295. https://doi.org/10.13182/NURETH20-40206
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    Covariances from model variation: application to quantities for astrophysics
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    The n_TOF NEAR Station Commissioning and first physics case
    In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:06009 (7 pp.). https://doi.org/10.1051/epjconf/202328406009
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    Evaluation of uncertainties in thermal-hydraulic analyses of PTS for the APAL European project
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  • Al-Yahia OS, Clifford I, Nikitin K, Ferroukhi H
    Parametric study on the modeling of the open passive containment cooling system (CWC)
    Presented at: The 13th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-13); September 5-10, 2022; Hsinchu.
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  • Babiano-Suarez V, Balibrea-Correa J, Caballero-Ontanaya L, Domingo-Pardo C, Ladarescu I, Lerendegui-Marco J, et al.
    First 80Se(n,γ) cross section measurement with high resolution in the full stellar energy range 1 eV - 100 keV and its astrophysical implications for the s-process
    In: Liu W, Wang Y, Guo B, Tang X, Zeng S, eds. Symposium on nuclei in the cosmos. 16th symposium on nuclei in the cosmos, NIC-XVI 2021. Les Ulis Cedex A: EDP Sciences; 2022:11026 (8 pp.). https://doi.org/10.1051/epjconf/202226011026
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  • D'Ambrosi V, Sercombe J, Beajoui S, Chaieb A, Baurens B, Largenton R, et al.
    P2M simulation exercise on past fuel melting irradiation experiments: main outcomes on fuel melting assessment in PWR fuel
    In: TopFuel 2022 light water reactor fuel performance conference. Illinois: American Nuclear Society; 2022:344-353. https://doi.org/10.13182/TopFuel22-38827
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  • Diomidis N, Pudollek S, Wittel M, Frankl M, Vasiliev A
    Post-closure canister degradation scenarios in deep geological disposal: preliminary definition and evaluation of potential impact on reactivity
    In: Nuclear Criticality Safety division topical meeting (NCSD 2022). La Grange Park: American Nuclear Society; 2022:(7 pp.). https://www.ans.org/pubs/proceedings/article-51979/.
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  • Fogliatto E, Clifford I, Ferroukhi H, Puragliesi R
    The influence of scaling on turbulent mixing in reactor pressure vessels and core-inlet flow distribution
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35578 (14 pp.).
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  • Hursin M, Mala P, Vasiliev A, Ferroukhi H, Liu Y, Choi S, et al.
    Comparison of CASMO-5, MPACT and Serpent 2 for the modeling of advanced BWR lattices
    In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:2762-2772.
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    In: International conference on physics of reactors. Proceedings of the international conference on physics of reactors, PHYSOR 2022. Downers Grove: American Nuclear Society; 2022:2762-2772. https://doi.org/10.13182/PHYSOR22-37760
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    Status of the WPEC subgroup 46 efficient and effective use of integral experiments for nuclear data validation
    In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:1095-1104. https://doi.org/10.13182/PHYSOR22-37758
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    Verification of legacy methodology of minimum critical mass estimation at PSI
    Presented at: GLOBAL 2022 - sustainable energy beyond the pandemic; July 6-8, 2022; Reims.
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  • Mager T, Hursin M, Fiorina C, Pautz A
    Development of a high fidelity model of the CROCUS experimental reactor
    In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:946-956. https://doi.org/10.13182/PHYSOR22-37250
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    The OECD NEA working party on nuclear criticality safety. Recent outcome, work in progress and outlook
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  • Nikitin K, Arnold B, Clifford I, Ferroukhi H
    CPR estimation by CTF subchannel code with machine learning support
    Presented at: The 13th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-13); September5-10, 2022; Hsinchu.
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  • Papadionysiou M, Seongchan K, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
    Coupling of COBRA-TF to nTRACER for full core high fidelity analysis of VVERs
    In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:586-595.
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  • Perret G, Clifford I, Ferroukhi H
    Bias and uncertainty considerations for trace predictions of RBHT reflood experiments
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  • Raffuzzi V, Sublet JC, Jouanne C, Koning A, Rochman D
    An iron evaluation story: from TALYS model parameters to validation on the ASPIS benchmark with the Monte Carlo code TRIPOLI-4®
    In: International conference on physics of reactors. Proceedings of the international conference on physics of reactors, PHYSOR 2022. Downers Grove: American Nuclear Society; 2022:1361-1370. https://doi.org/10.13182/PHYSOR22-37310
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    An iron evaluation story: from TALYS model parameters to validation on the ASPIS benchmark with the Monte Carlo code TRIPOLI-4®
    In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:1361-1370.
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  • Scolaro A, Fiorina C, Siefman D, Hursin M, Pautz A
    Bayesian data assimilation for fuel performance based on OFFBEAT
    In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:3656-3665. https://doi.org/10.13182/PHYSOR22-37357
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    Pre-release validation database for the multi-dimensional fuel performance code OFFBEAT
    In: International conference on physics of reactors. Proceedings of the international conference on physics of reactors, PHYSOR 2022. Downers Grove: American Nuclear Society; 2022:2914-2923. https://doi.org/10.13182/PHYSOR22-37789
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  • Sublet JC, Koning A, Rochman D, Gilbert MR, Kahler AC, Jouanne C, et al.
    Multifaceted coded nuclear data libraries assemblage, verification and validation: TENDL-2021
    In: International conference on radiation shielding and topical meeting of the radiation protection and shielding division. Proceedings of the 14th international conference on radiation shielding and 21st topical meeting of the radiation protection and shielding division, ICRS 2022/RPSD 2022. American Nuclear Society; 2022:308-311. https://doi.org/10.13182/ICRSRPSD22-39025
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  • Zahur A, Park J, Cherezov A, Jo Y, Lee D
    Reactivity initiated accident uncertainty quantification for fuel assembly with subchannel code
    In: International conference on physics of reactors. Proceedings of the international conference on physics of reactors, PHYSOR 2022. Downers Grove: American Nuclear Society; 2022:1667-1676. https://doi.org/10.13182/PHYSOR22-37528
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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: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:06011 (8 pp.). https://doi.org/10.1051/epjconf/202124706011
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    EUROSAFE: fostering the sharing of nuclear expertise
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  • Cozzo C, Lind T, Bertsch J, Nichenko S, Girardin G
    Quantifying the benefits of the reduced oxidation kinetics in chromium-coated cladding: a parametric study
    In: Vázquez-Rodriguez C, Jiménez Carrascosa A, Estevez Albuja S, Duran Vinuesa LF, eds. Book of Proceedings. European nuclear young generation forum 2021. sine loco: European Nuclear Young Generation Forum; 2021:245-248.
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    An initiative for the development and application of open-source multi-physics simulation in support of R&D and E&T in Nuclear Science and Technology
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    Impact of various source of covariance information on integral parameters uncertainty during depletion calculations with CASMO-5
    In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:09005 (10 pp.). https://doi.org/10.1051/epjconf/202124709005
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    Monte Carlo analysis of sub-pin resolved power behaviour in modern BWR assembly designs
    In: Proceedings of the international conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2021). Illinois: American Nuclear Society (ANS); 2021:758-767. https://doi.org/10.13182/M&C21-33772
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    Validation of axial void profile measured by neutron noise techniques in crocus
    In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:08004 (8 pp.). https://doi.org/10.1051/epjconf/202124708004
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  • Konarski P, Cozzo C, Khostov G, Ferroukhi H
    Extension of Falcon's modelling capabilities to dry storage: development of a new model for hydrogen behavior in duplex claddings
    In: TopFuel2021. Brussels: European Nuclear Society; 2021:(10 pp.).
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  • Lamirand V, Rais A, Pakari O, Hursin M, Laureau A, Pohlus J, et al.
    Analysis of the first COLIBRI fuel rods oscillation campaign in the CROCUS reactor for the European project CORTEX
    In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:21010 (9 pp.). https://doi.org/10.1051/epjconf/202124721010
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    Validation of the gen-foam model of the crocus experimental reactor
    In: Proceedings of the international conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2021). Illinois: American Nuclear Society (ANS); 2021:738-747. https://doi.org/10.13182/M&C21-33754
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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
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    Core SIM+ simulations of COLIBRI fuel rods oscillation experiments and comparison with measurements
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  • Papadionysiou M, Seongchan K, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
    Coupling of nTRACER to COBRA-TF for high-fidelity analysis of VVERs
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    Validation of the high-resolution code nTRACER against VVER-1000 hot zero power measurements
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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
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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
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  • Scolaro A, Fiorina C, Van Uffelen P, Schubert A, Clifford I, Pautz A
    Coupling methodology between TRANSURANUS and the multi-dimensional fuel performance code OFFBEAT
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  • Szabolcs Ványi A, Hursin M, Czifrus S
    Investigation of recently introduced diffusion coefficient generation methods
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  • Tasakos T, Ioannou G, Verma V, Alexandridis G, Dokhane A, Stafylopatis A
    Deep learning-based anomaly detection in nuclear reactor cores
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  • Torres LA, Chionis D, Montalvo C, Dokhane A, García-Berrocal A
    Neutron noise spectral features of simulated mechanical and thermal-hydraulic perturbations in a PWR core
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  • Valentine T, Avramova M, Fleming M, Hursin M, Ivanov K, Petruzzi A, et al.
    Overview of the OECD-NEA expert group on multi-physics experimental data, benchmarks and validation
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  • Vasiliev A, Pecchia M, Rochman D, Ferroukhi H
    Enhancement of validation studies for reactor dosimetry and activation predictions with the nuclear data sampling methodology
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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
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  • 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
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  • 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
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  • Ambrožič K, Lamirand V, Hübner S, Hursin M, Rais A, Pakari O, et al.
    Noise analysis techniques of in-core modulation experiments for the European project CORTEX
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  • 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
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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
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  • Chiaveri E, Aberle O, Alcayne V, Amaducci S, Andrzejewski J, Audouin L, et al.
    Status and perspectives of the neutron time-of-flight facility n_TOF at CERN
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  • Clifford I, Zerkak O, Ferroukhi H
    Making the switch from pipe to vessel components
    In: Advances in thermal hydraulics (ATH'20). La Grange Park: American Nuclear Society; 2020:157-170.
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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
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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 Sciences; 2020:05014 (5 pp.). https://doi.org/10.1051/epjconf/202023905014
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  • Fischer U, Avrigeanu M, Avrigeanu V, Konobeyev A, Kodeli I, Leeb H, et al.
    Nuclear data activities of the EUROfusion consortium
    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; 2020:21001 (7 pp.). https://doi.org/10.1051/epjconf/202023921001
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  • Lamirand V, Rais A, Hübner S, Lange C, Pohlus J, Paquee U, et al.
    Neutron noise experiments in the AKR-2 and CROCUS reactors for the European project CORTEX
    In: Lyoussi A, Giot M, Carette M, Jenčič I, Reynard-Carette C, Vermeeren L, et al., eds. ANIMMA 2019 - advancements in nuclear instrumentation measurement methods and their applications. Vol. 225. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2020:04023 (6 pp.). https://doi.org/10.1051/epjconf/202022504023
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  • Lamirand V, Frajtag P, Godat D, Pakari O, Laureau A, Rais A, et al.
    The COLIBRI experimental program in the CROCUS reactor: characterization of the fuel rods oscillator
    In: Lyoussi A, Giot M, Carette M, Jenčič I, Reynard-Carette C, Vermeeren L, et al., eds. ANIMMA 2019 - advancements in nuclear instrumentation measurement methods and their applications. Vol. 225. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2020:04020 (5 pp.). https://doi.org/10.1051/epjconf/202022504020
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  • Laureau A, Lamirand V, Rochman D, Pautz A
    Bayesian Monte Carlo assimilation for the PETALE experimental programme using inter-dosimeter correlation
    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; 2020:18004 (4 pp.). https://doi.org/10.1051/epjconf/202023918004
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  • 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 Sciences; 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 Sciences; 2020:07003 (5 pp.). https://doi.org/10.1051/epjconf/202023907003
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  • Mendoza E, Alcayne V, Cano-Ott D, Kimura A, Skarbeli AV, Aberle O, et al.
    Study of photon strength functions of 241Pu and 245Cm from neutron capture measurements
    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; 2020:05006 (6 pp.). https://doi.org/10.1051/epjconf/202023901015
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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 Sciences; 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
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  • Mora DF, Niffenegger M, Mukin R
    Crack propagation modeling in a PWR under PTS Using XFEM
    In: 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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  • 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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  • Pakari O, Lamirand V, Vandereydt B, Vitullo F, Hursin M, Kong C, et al.
    Design and simulation of gamma spectrometry experiments in the CROCUS reactor
    In: Lyoussi A, Giot M, Carette M, Jenčič I, Reynard-Carette C, Vermeeren L, et al., eds. ANIMMA 2019 - advancements in nuclear instrumentation measurement methods and their applications. Vol. 225. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2020:04016 (6 pp.). https://doi.org/10.1051/epjconf/202022504016
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  • Sublet JC, Koning A, Rochman D, Gilbert MR, Kahler AC, Jouanne C, et al.
    Multitaceted coded nuclear data libraries assemblage, verification and validation: TENDL-2019
    In: Fabian J, Michal R, Corradini ML, Martin W, Klein AC, Bibao y Leon S, et al., eds. 2020 transactions of the American Nuclear Society Winter Meeting, ANS 2020. Vol. 123. Transactions of the American Nuclear Society. Illinois: American Nuclear Society; 2020:1227-1230. https://doi.org/10.13182/T123-33321
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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, 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, 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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  • Vitullo F, Lamirand V, Mosset J-B, Frajtag P, Pakari O, Perret G, et al.
    Developing and testing a miniature fiber-coupled scintillator for in-core neutron counting in CROCUS
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2019

  • 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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  • Alcayne V, Kimura A, Mendoza E, Cano-Ott D, Martínez T, Aberle O, et al.
    Measurement of the 244Cm and 246Cm neutron-induced capture cross sections at the n_TOF facility
    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; 2019:03008 (8 pp.). https://doi.org/10.1051/epjconf/201921103008
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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
    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; 2019:169-173. https://doi.org/10.1007/978-3-030-22204-8_18
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  • Barbagallo M, Aberle O, Alcayne V, Andrzejewski J, Audouin L, Bécares V, et al.
    (n,cp) reactions study at the n_TOF facility at CERN: results for the cosmological lithium problem
    In: Cerutti F, Ferrari A, Kawano T, Salvat-Pujol F, Talou P, eds. Proceedings of the 15th international conference on nuclear reaction mechanisms. Geneva: CERN; 2019:259-264.
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  • Chionis D, Dokhane A, Ferroukhi H, Pautz A
    Spatial localization of perturbation propagation in LWRs using causality and connectivity analysis
    In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). La Grange Park, USA: American Nuclear Society (ANS); 2019:1960-1969.
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  • Clifford I, Cozzo C, Ferroukhi H
    First assessments of the dynamic gap conductance model in TRACE
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park, USA: American Nuclear Society (ANS); 2019:4624-4636.
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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
    In: Global/top fuel 2019. LaGrange Park, IL, USA: American Nuclear Society (ANS); 2019:643-647.
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  • Dokhane A, Hursin M, Vasiliev A, Ferroukhi H, Grandi G
    Impact of implicit effects on uncertainties in SPERT-III Rod Ejection Accident experiments
    In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). La Grange Park: American Nuclear Society; 2019:2765-2774.
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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
    In: International conference on mathematics computational methods applied to nuclear science and engineering (M&C 2019). La Grange Park: American Nuclear Society (ANS); 2019:(8 pp.).
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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
    In: International conference on mathematics computational methods applied to nuclear science and engineering (M&C 2019). La Grange Park: American Nuclear Society (ANS); 2019:(9 pp.).
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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
    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; 2019:03003 (5 pp.). https://doi.org/10.1051/epjconf/201921103003
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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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  • 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 (ANS); 2019:1640-1649.
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  • Massimi C, Aberle O, Alcayne V, Andrzejewski J, Audouin l., Bécares V, et al.
    Data for the s process from n_TOF
    In: Formicola A, Junker M, Gialanella L, Imbriani G, eds. Nuclei in the cosmos XV. Vol. 219. Springer proceedings in physics. Cham: Springer; 2019:63-70. https://doi.org/10.1007/978-3-030-13876-9_11
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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.
    Screening analysis for pressurized thermal shock (PTS) transient scenarios
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park, USA: American Nuclear Society (ANS); 2019:2536-2549.
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  • Niffenegger M, Garrido OC, Mora DF, Qian G, Mukin R, Sharabi M, et al.
    Uncertainties in pressurized thermal shock analyses
    In: Design and analysis: 4th international symposium on coke drum life cycle management. Vol. 3. PVP - American society of mechanical engineers. Pressure vessels and piping division. sine loco: American Society of Mechanical Engineers (ASME); 2019:PVP2019-94076 (10 pp.). https://doi.org/10.1115/PVP2019-94076
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  • Nikitin K, Clifford I, Ferroukhi H
    PMSYS: plant management system as a part of Swiss Simulation Platform
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). LaGrange Park, USA: American Nuclear Society (ANS); 2019:2943-2954.
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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
    In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). La Grange Park, USA: American Nuclear Society (ANS); 2019:700-709.
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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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  • 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
    In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS); 2019:2209-2222.
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  • Rais A, Lamirand V, Pakari O, Laureau A, Pohlus J, Pohl C, et al.
    Towards the validation of neutron noise simulators: qualification of data acquisition systems
    In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). Illinois: American Nuclear Society (ANS); 2019:2638-2647.
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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.
    DORA PSI
  • 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.
    DORA PSI
  • Siefman D, Hursin M, Pautz A
    Data assimilation of post irradiation examination experiments to adjust fission yields
    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; 2019:13004 (4 pp.). https://doi.org/10.1051/epjconf/202023913004
    DORA PSI
  • Tagliente G, Aberle O, Alcayne V, Andrzejewski J, Audouin L, Babiano-Suarez V, et al.
    Nuclear astrophysics at n_TOF facility, CERN
    In: Cerutti F, Ferrari A, Kawano T, Salvat-Pujol F, Talou P, eds. Proceedings of the 15th international conference on nuclear reaction mechanisms. Geneva: CERN; 2019:251-258.
    DORA PSI
  • Tassan-Got L, Colonna N, Diakaki M, Eleme Z, Manna A, Sekhar A, et al.
    Fission program at n_TOF
    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; 2019:03006 (9 pp.). https://doi.org/10.1051/epjconf/201921103006
    DORA PSI
  • 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
    In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). La Grange Park: American Nuclear Society (ANS); 2019:1124-1133.
    DORA PSI
  • Wolfertz A, Adams R, Perret G
    First tests of a gamma-blind fast neutron detector prototype based on ZnS and wavelength-shifting fibers
    In: Annual meeting 2019. Vol. 120. Transactions of the American Nuclear Society. La Grange Park: American Nuclear Society; 2019:426-428.
    DORA PSI

2018

  • 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; 2018:03004 (5 pp.). https://doi.org/10.1051/epjconf/201817803004
    DORA PSI
  • Chionis D, Dokhane A, Ferroukhi H, Girardin G, Pautz A
    PWR neutron noise phenomenology: part I - simulation of stochastic phenomena with simulate-3K
    In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018:1001-1012.
    DORA PSI
  • 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.
    DORA PSI
  • Cozzo C, Khvostov G
    ATF developments in FALCON V1 at PSI
    In: Topfuel 2018. Part 4. Brussels: European Nuclear Society; 2018:A0112 (9 pp.).
    DORA PSI
  • 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
    DORA PSI
  • 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.
    DORA PSI
  • Dokhane A, Chionis D, Ferroukhi H
    Towards systematic and continuous tracking of neutron and process noise signatures during LWR operation
    In: International conference on physics of reactors (PHYSOR 2018). Reactor physics paving the way towards more efficient systems. Red Hook: Curran Associates, Inc.; 2018:3005-3016.
    DORA PSI
  • 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.).
    DORA PSI
  • 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.).
    DORA PSI
  • Hursin M, Siefman D, Perret G, Pautz A
    Representativity analysis of the LWR-PROTEUS Phase II experiments using SHARKX stochastic sampling method
    In: ANS international conference on best-estimate plus uncertainties methods (BEPU-2018). La Grange Park: American Nuclear Society; 2018:277 (12 pp.).
    DORA PSI
  • Hursin M
    The importance of experimental uncertainty in the BEPU Approach
    In: ANS international conference on best-estimate plus uncertainties methods (BEPU-2018). La Grange Park: American Nuclear Society; 2018:KNA4 (12 pp.).
    DORA PSI
  • Jung B, Vasiliev A, Pecchia M, Ferroukhi H
    Optimization and sensitivity studies towards PWR structures activation characterization using the MCNP code
    Presented at: 2018 student conference; April 5-7, 2018; University of Florida, Gainesville, FL, USA.
    DORA PSI
  • 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
    DORA PSI
  • 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.).
    DORA PSI
  • Mukin R, Rochman D, Clifford I, Vasiliev A, Ferroukhi H
    Effect of nuclear data on the DNBR prediction with subchannel code COBRA-TF
    In: ANS international conference on best-estimate plus uncertainties methods (BEPU-2018). La Grange Park: American Nuclear Society; 2018:285 (6 pp.).
    DORA PSI
  • 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
    DORA PSI
  • 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
    DORA PSI
  • 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
    In: ANS international conference on best-estimate plus uncertainties methods (BEPU-2018). La Grange Park: American Nuclear Society; 2018:2018-124 (11 pp.).
    DORA PSI
  • 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
    DORA PSI
  • 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.).
    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
    In: PHYSOR 2018: reactor physics paving the way towards more efficient systems. International Conference on Physics of Reactors, PHYSOR 2018: Reactor Physics Paving the Way Towards More Efficient Systems. Red Hook: Curran Associates, Inc.; 2018:(12 pp.).
    DORA PSI
  • Perret G, Rahman S, Wicaksono D
    Deterministic sampling and Gaussian Process metamodel approach applied to a station black out accident model
    Presented at: ANS best estimate plus uncertainty international conference (BEPU 2018); May 13-18, 2018; Lucca, Italy.
    DORA PSI
  • Perret G, Wicaksono D
    Global sensitivity analysis and registration strategy for temperature profiles of reflood experiment simulations
    In: ANS international conference on best-estimate plus uncertainties methods (BEPU-2018). La Grange Park: American Nuclear Society; 2018:098 (14 pp.).
    DORA PSI
  • Puragliesi R, Mukin R, Clifford I, Ferroukhi H, Seidl M
    Computational fluid dynamics as a tool for deriving subchannel model parameters - The PSBT case study
    In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Computational fluid dynamics (CFD); nuclear education and public acceptance. Vol. 8. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-81743 (13 pp.). https://doi.org/10.1115/ICONE26-81743
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Janin D, Seidl M
    Best estimate plus uncertainty analysis for the 244CM prediction in spent fuel characterization
    Presented at: ANS best estimate plus uncertainty international conference (BEPU 2018); May 13-18, 2018; Lucca, Italy.
    DORA PSI
  • Scolaro A, Clifford I, Fiorina C, Pautz A
    First steps towards the development of a 3D nuclear fuel behaviour solver with OpenFOAM
    In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Nuclear fuel and material, reactor physics, and transport theory. Vol. 3. sine loco: American Society of Mechanical Engineers (ASME); 2018:ICONE26-82381 (10 pp.). https://doi.org/10.1115/ICONE26-82381
    DORA PSI
  • Siefman D, Hursin M, Aufiero M, Bidaud A, Pautz A
    Convergence analysis and criterion for data assimilation with sensitivities from Monte Carlo neutron transport codes
    In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018:(10 pp.).
    DORA PSI
  • Sublet J-C, Koning A, Rochman D
    TENDL-2017: the making of multi-faceted technological nuclear data library
    In: Radiation protection and shielding division 20th topical meeting. Illinois: American Nuclear Society (ANS); 2018:(7 pp.).
    DORA PSI
  • Tambouratzis T, Chionis D, Dokhane A
    General regression neural networks for the concurrent, timely and reliable identification of detector malfunctions and/or nuclear reactor deviations from steady-state operation
    In: Sundaram S, ed. Proceedings of the 2018 IEEE symposium series on computational intelligence (SSCI 2018). Piscataway: IEEE; 2018:524-531. https://doi.org/10.1109/SSCI.2018.8628700
    DORA PSI
  • Vasiliev A, Herrero J, Rochman D, Pecchia M, Ferroukhi H, Caruso S
    Criticality safety evaluations for the concept of Swiss PWR spent fuel geological repository
    In: ANS international conference on best-estimate plus uncertainties methods (BEPU-2018). La Grange Park: American Nuclear Society; 2018:229 (12 pp.).
    DORA PSI
  • Vasiliev A, Rochman D, Pecchia M, Ferroukhi H
    On the importance of the neutron scattering angular distributions for the LWR fast neutron dosimetry
    In: International conference on physics of reactors (PHYSOR 2018). Reactor physics paving the way towards more efficient systems. Red Hook: Curran Associates, Inc.; 2018:3686-3697.
    DORA PSI


Impact of Nuclear Data Uncertainty in the Modeling of Recoil Atom Energy Distributions in Silicon
P.J. Griffin, A. Koning, D. Rochman
ANS RPSD 2018, 20th Topical Meeting of the Radiation Protection & Shielding Division of ANS Santa Fe, NM, August 26 31, 2018

Effect of Nuclear Data on the DNBR Preduction with Subchannel code COBRA-TF
R. Mukin, D. Rochman, I. Clifford, A. Vasiliev, H. Ferrouhki
BEPU 2018: Best Estimate Plus Uncertainty International Conference Lucca, Italy, May 13-18, 2018

Global Sensitivity Analysis and Registration Strategy for Temperature Profiles of Reflood Experiment Simulations
G. Perret, D. Wicaksono
BEPU 2018: Best Estimate Plus Uncertainty International Conference Lucca, Italy, May 13-18, 2018

Criticality Safety Evaluations for the concept of Swiss PWR Soent Fuel Geological Repository
A. Vasiliev, J. Herrero, D. Rochman, M. Pecchia, H. Ferroukhi, S. Caruso
BEPU 2018: Best Estimate Plus Uncertainty International Conference Lucca, Italy, May 13-18, 2018

Representativity Analysis of the LWR-PROTEUS Phase II Experiments Using SHARKX Stochastic Sampling Method
M. Hursin, D. Siefman, G. Perret, A. Pautz
BEPU 2018: Best Estimate Plus Uncertainty International Conference Lucca, Italy, May 13-18, 2018

The Importance of Experimental Uncertainty in the BEPU Approach
M. Hursin
BEPU 2018: Best Estimate Plus Uncertainty International Conference Lucca, Italy, May 13-18, 2018

Determination of Sobol Sensitivity Indices for Correlated Inputs with Shark-X
M. Hursin, D. Siefman, G. Perret, D. Rochman, A. Vasiliev, H. Ferrouhki
Physor 2018: Reactor Physics Paving The Way Towards More Efficient Systems Cancun, Mexico, April 22-26, 2018

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
Physor 2018: Reactor Physics Paving The Way Towards More Efficient Systems Cancun, Mexico, April 22-26, 2018


Studies On The Effects Of Local Power Peaking On Heat Transfer Under Dryout Conditions In Bwrs
I.Clifford, M. Pecchia, R. Mukin, H. Ferroukhi, A. Gorzel
Physor 2018: Reactor Physics Paving The Way Towards More Efficient Systems Cancun, Mexico, April 22-26, 2018


Towards Systematic And Continuous Tracking Of Neutron And Process Noise Signatures During Lwr Operation
A. Dokhane, D. Chionis, H. Ferroukhi
Physor 2018: Reactor Physics Paving The Way Towards More Efficient Systems Cancun, Mexico, April 22-26, 2018


On The Importance Of The Neutron Scattering Angular Distributions For The Lwr Fast Neutron Dosimetry
A. Vasiliev, D. Rochman, M. Pecchia, H. Ferroukhi
Physor 2018: Reactor Physics Paving The Way Towards More Efficient Systems Cancun, Mexico, April 22-26, 2018

Optimization And Sensitivity Studies Towards Pwr Structures Activation Characterization Using The Mcnp Code
B. Jung, A. Vasiliev, M. Pecchia, H. Ferroukhi
Ans Student Conference 2018, University of Florida, Gainesville Fl, Usa, April 5 - 7 2018,

2017

Sic Caldding Behaviour: Experiments And Modelling At Psi
C. Cozzo, J. Bertsch, L. Fave, S. Rahman, A. Dokhane, M. Krack, M.A. Pouchon, Y. Dai, J-C. Chen, M. Pytel
Proc. 2017 Water Reactor Fuel Performance Meeting (Wrfpm2017), Jeju Island, Korea, September 10-14, 2017


New Insights In The Fuel Grain Subdivision During In-Plant Irraditaion Up To High Burnup
M. Chollet, C. Cozzo, J. Bertsch, M. Martin, D. Grolimund, V-A. Samson
Proc. 2017 Water Reactor Fuel Performance Meeting (Wrfpm2017), Jeju Island, Korea, September 10-14, 2017


Thermal Mixing Assessment Using 3d Thermal-Hydraulic And Cfd Codes
R. Mukin, R. Puragliesi, S. C. Ceuca, H. Austregesilo, A. Bousbia Salah
Proc. 17th Int. **Topical Meeting On Nuclear Reactor Thermal Hydraulics (Nureth-17), Xian, China, 3-9 September 2017


Thermal Hydraulic Analysis Of Pwr Assembly Bowing Using Subchannel Code Cobra-Tf
R. Mukin, I. Clifford, H. Ferroukhi, M. Seidl
Proc. 17th Int. **Topical Meeting On Nuclear Reactor Thermal Hydraulics (Nureth-17), Xian, China, 3-9 September 2017


Characterization Of The Energy-Dependent Uncertainty And Correlation In Silicon Neutron Displacement Damage Metrics
P. Griffin, D. Rochman, A. Koning
Epj Web of Conferences 146, 02008, Nd2016 (2017)


Talys/Tendl Verification And Validation Processes: Outcomes And Recommendations
M. Fleming, J-C. Sublet, M. R. Gilbert, A. Koning, D. Rochman
Epj Web of Conferences 146, 02033, (2017)


Propagation Of Nuclear Data Uncertainties For Fusion Power Measurements
H.Sjostrand, S. Conroy, P. Helgesson, S. A. Hernandez, A. Koning, S. Pomp, D. Rochman
Epj Web of Conferences 146, 02034 (2017)


The Role Of Nuclear Data For Fusion Nuclear Technology
U. Fischer, M. Angelone, M. Avrigeanu, V. Avrigeanu, C. Bachmann, N. Dzysiuk, M. Fleming, A. Konobeev, I. Kodeli, A. Koning, H. Leeb, D. Leichtle, F. Ogando, P. Pereslavtsev, D. Rochman, P. Sauvan, S. Simakov
Proc. Int. Conf. Fusion Nuclear Technology Conference, Kyoto, September 25 -29, 2017


Trace/S3k Code Coupling Simulations Of A Bwr/4 Anticipated Transient Without Scram
Y. Aounallah
Proc. Canadian Nuclear Soeciety Meeting Niagara Falls, Canada, June 4-7, 2017


Simulations With Trace Of A Bwr/4 Steam Line Break Under Hot Standby Conditions
Y. Aounallah
Proc. Canadian Nuclear Society Meeting Niagara Falls, Canada, June 4-7, 2017


Simulate-3k Analyses Of Neutron Noise Response To Fuel Assembly Vibrations And Thermal-Hydraulics Parameters Fluctuations
D. Chionis, A. Dokhane, L. Belblidia, M. Pecchia, G. Girardin, H. Ferroukhi, A. Pautz
Proc. Mathematics & Computations M&C 2017, Jeju, Korea, April 16-20, 2017


Nodal And Pin-By-Pin Calculations Comparison With Codes Simulate-5 And Dyn3d
P. Mala, A. Pautz, S. Canepa, H. Ferroukhi
Proc. Mathematics & Computations M&C 2017, Jeju, Korea, April 16-20, 2017


Bowing Effects On Power And Burn-Up Distributions For Simplified Full Pwr And Bwr Cores
D. Rochman, P. Mala, H. Ferroukhi, A. Vasiliev, M. Seidl, D. Janin, J. Li
Proc. Mathematics & Computations M&C 2017, Jeju, Korea, April 16-20, 2017


Nuclear Data Uncertainty Decomposition For Spert-Iii Ria Experiments Using Simulate-3k And Shark-X
A. Dokhane, G. Grandi, O. Leray, D. Rochman, A. Vasiliev, H. Ferroukhi
Proc. Mathematics & Computations M&C 2017, Jeju, Korea, April 16-20, 2017

2016

Simulations Of Level-Swell Experiments With Trace
Y. Aounallah
Nuthos-11, Gyeongju, Korea, October 9-13, 2016


System Code Validation Series Based On A Consistent Plant Nodalisation Of The Rosa/Lstf Integral Test Facility Using Trace V5.0 Patch 4
I. Clifford, O. Zerkak, A. Pautz
Nuthos-11, Gyeongju, Korea, October 9-13, 2016


Modeling And Analysis Of Selected Oecd Pkl3 Station-Blackout Experiments Using Trace
R. Mukin, O. Zerkak, A. Pautz
Nuthos-11, Gyeongju, Korea, October 9-13, 2016


Influence Of Urans Turbulence Models On In-Vessel Flow Mixing During Cold Leg Accumulator Injection
R. Puragliesi, O. Zerkak, A. Pautz
Nuthos-11, Gyeongju, Korea, October 9-13, 2016


Bayesian Calibration Of Thermal-Hydraulics Model With Time-Dependent Output
D. Wicaksono, O. Zerkak, A. Pautz
Nuthos-11, Gyeongju, Korea, October 9-13, 2016


Evaluation Of Deterministic Sampling For Uncertainty Quantification In A Probabilistic Accident Analysis Model
S. Rahman, D.R. Karanki, D. Wicaksono, O. Zerkak, V.N. Dang
Nuthos-11, Gyeongju, Korea, October 9-13, 2016


The Tendl Library: Hope, Reality And Future
D. Rochman, A.J. Koning, J.Ch. Sublet, M. Fleming, E. Bauge, S. Hilaire, P. Romain, B. Morillon, H. Duarte, S. Goriely, S.C. Van Der Marck, H. SjöStrand, S. Pomp, N. Dzysiuk, O. Cabellos, H. Ferroukhi, A. Vasiliev
Proc. Nuclear Data 2016, Bruges, Belgium, September 11-16, 2016


Impact Of Nuclear Data Uncertainty On Safety Calculations For Spent Nuclear Fuel Geological Disposal
J.J. Herrero, D. Rochman, O. Leray, A. Vasiliev, M. Pecchia, H. Ferroukhi, S. Caruso
Proc. Nuclear Data 2016, Bruges, Belgium, September 11-16, 2016 (Epj Web of Conferences 146, 09028, 2017)


Impact Of Implicit Effects On Uncertainties And Sensitivities Of The Doppler Coefficient Of A Lwr Pin Cell
M. Hursin, O. Leray, G.Perret, A.Pautz, F. Bostelmann, A. Aures, W. Zwermann
Proc. Nuclear Data 2016, Bruges, Belgium, September 11-16, 2016 (Epj Web of Conferences 146, 09034, 2017)


Fission Yield Covariances For Jeff: A Bayesian Monte Carlo Method
O. Leray, D. Rochman, M. Fleming, J-C. Sublet, A. Koning, A. Vasiliev, H. Ferroukhi
Proc. Nuclear Data 2016, Bruges, Belgium, September 11-16, 2016 (Epj Web of Conferences 146, 09023, 2017)


Full Core Loca Analysis For Bwr/6 - Methodology And First Results
C. Cozzo, A. Epiney, S. Canepa, H. Ferroukhi, O. Zerkak, G. Khvostov,V. Brankov, A. Gorzel
Topfuel 2016, Boise, Idaho, Usa, September 11-16, 2016


Comparison Of Fission Yield Perturbation Methodologies On Nuclide Composition For A Pwr Uo2 Fuel Assembly
O. Leray, L. Fiorito, D. Rochman, H. Ferroukhi, A. Pautz, A. Stankovskiy, G. Van Den Eynde
Physor 2016, Sun Valley, Idaho, Usa, May 1-5, 2016


Validation Of Simulate-3k Against Spert-Iii Ria Experiments With Quantification Of Nuclear Data Uncertainties
A. Dokhane, O. Leray, D. Rochman, H. Ferroukhi, A. Pautz
Physor 2016, Sun Valley, Idaho, Usa, May 1-5, 2016


Solution Of The Beavrs Benchmark Using Casmo-5 / Simulate-5 Code Sequence
V. Bykov, A. Vasiliev, H. Ferroukhi, A. Pautz
Physor 2016, Sun Valley, Idaho, Usa, May 1-5, 2016


On Causality Analysis Of Nuclear Reactor Noise Using Partial Directed Coherence
D. Chionis, A. Dokhane, H. Ferroukhi, A. Pautz
Physor 2016, Sun Valley, Idaho, Usa, May 1-5, 2016


Comparative Study Of Casmo-5/Simulate-5 And Ntracer For Epr Core Analyses
S. Canepa, H. Ferroukhi, R. Min, H.G. Joo
Icapp 2016, San Francisco, Ca, Usa, April 17-20, 2016


Towards Analysis Of The Bowing Effect On Burnt Nuclear Fuel Compositions Using Serpent
J. Li, D. Rochman, J. Herrero, H. Ferroukhi, A. Vasiliev, A. Pautz
American Nuclear Society 2016 Student Conference, University of Wisconsin, Madison, Usa, March 31-April 3, 2016


Extention Of Psi Fnf Modeling Methodology Validation Using Bwr Dosimetry Data
R. Savelli, A. Vasiliev, H. Ferroukhi, A. Pautz
American Nuclear Society 2016 Student Conference, University of Wisconsin, Madison, Usa, March 31-April 3, 2016

2015

Complink: A Versatile Tool For Automatizing The Representation Of Material Data In Mcnp Models
M. Pecchia, J. J. Herrero, H. Ferroukhi, A. Vasiliev, S. Canepa, A. Pautz
Proc. Int. Conf. Nuclear Criticality Safety, Icnc 2015, Charlotte, Nc, Usa, September 13-17, 2015


Towards Application Of Neutron Cross-Section Uncertainty Propagation Capability In The Criticality Safety Methodology
A. Vasiliev, D. Rochman, T. Zhu, M. Pecchia, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Nuclear Criticality Safety, Icnc 2015, Charlotte, Nc, Usa, September 13-17, 2015


Computational Scheme For Burnup Credit Applied To Long Term Waste Disposal
J.J. Herrero, M. Pecchia, H. Ferroukhi, S. Canepa, A. Vasiliev, S. Caruso
Proc. Int. Conf. Nuclear Criticality Safety, Icnc 2015, Charlotte, Nc, Usa, September 13-17, 2015


Modeling Of Axial Distribution Of Released Fission Gas In Kkl Bwr Fuel Rods During Base Irradiation
V. Brankov, G. Khvostov, K. Mikityuk, A. Pautz, R. Restani, S. Abolhassani, G. Ledergerber, W. Wiesenack
Proc. Water Reactor Fuel Performance Meeting Topfuel 2015, Zurich, Switzerland, September 13-17, 2015


Ranking Of Uncertain Parameters For Dynamic Event Tree Analysis: A Case Study Based On A Station Blackout Scenario
S. Rahman, D.R. Karanki, A. Epiney, O. Zerkak, V.N. Dang
Proc. Int. Top.Meetg. Nucl. Reactor Thermal-Hydraulics Nureth-16, Chicago, Usa, August 30 - September 4, 2015


Assessment Of Openfoam Cfd Toolbox For Gravity Driven Mixing Flows In A Reactor Pressure Vessel
R. Puragliesi, Q. Zhou, O. Zerkak, A. Pautz
Proc. Int. Top.Meetg. Nucl. Reactor Thermal-Hydraulics Nureth-16, Chicago, Usa, August 30 - September 4, 2015


Computational Fluid Dynamics Analysis Of The Fluid Flow And Heat Transfer In The Core Bypass Region Of A Pwr
I. Clifford, A. Vasiliev, O. Zerkak, H. Ferroukhi, A. Pautz
Proc. Int. Top.Meetg. Nucl. Reactor Thermal-Hydraulics Nureth-16, Chicago, Usa, August 30 - September 4, 2015


Methodology For Global Sensitivity Analysis Of Transient Code Output Applied To A Reflood Experiment Model Using Trace
D. Wicaksono, O. Zerkak, A. Pautz
Proc. Int. Top.Meetg. Nucl. Reactor Thermal-Hydraulics Nureth-16, Chicago, Usa, August 30 - September 4, 2015


Trace/Simulate-3k Analysis Of The Nea/Oecd Oskarshamn-2 Stability Benchmark
A. Dokhane, O. Zerkak, H. Ferroukhi, I. Gajev, J. Judd, T. Kozlowski
Proc. Int. Top.Meetg. Nucl. Reactor Thermal-Hydraulics Nureth-16, Chicago, Usa, August 30 - September 4, 2015


Towards A Consolidated Approach For The Validation Of Plant System Codes And Models: A Case Study For A Bwr Fast Depressurization Event
A. Epiney, S. Canepa, O. Zerkak, H. Ferroukhi
Proc. Int. Top.Meetg. Nucl. Reactor Thermal-Hydraulics Nureth-16, Chicago, Usa, August 30 - September 4, 2015


Development, Verification And Test Application Of A Hybrid Casmo-5/Serpent Depletion Scheme
O. Leray, M. Pecchia, A. Vasiliev, H. Ferroukhi, A. Pautz, H.Perrier
Proc. Joint Int. Conf. On Mathematics And Computation, Supercomputing in Nuclear Applications And The Monte Carlo Method, M&C+Sna+Mc 2015, Tennessee, Usa, April 19-23, 2015


Preparation Of Pin-By-Pin Nuclear Libraries With Superhomogenization Method For Ntracer And Dort Core Calculations
P. Mala, S. Canepa, H. Ferroukhi, A. Pautz
Proc. Joint Int. Conf. On Mathematics And Computation, Supercomputing in Nuclear Applications And The Monte Carlo Method, M&C+Sna+Mc 2015, Tennessee, Usa, April 19-23, 2015


Bwr Full Core Analysis With Serpent/Simulate-3 Hybrid Stochastic/Determinstic Code Sequence
M. Hursin, L. Rossinelli, H. Ferroukhi And A. Pautz
Proc. Joint Int. Conf. On Mathematics And Computation, Supercomputing in Nuclear Applications And The Monte Carlo Method, M&C+Sna+Mc 2015, Tennessee, Usa, April 19-23, 2015


Scalability Benchmarking Methodology For Hybrid Parallel Core Calculations With The Code Ntracer
S. Canepa, M. Krack, H. Ferroukhi, A. Pautz
Proc. Joint Int. Conf. On Mathematics And Computation, Supercomputing in Nuclear Applications And The Monte Carlo Method, M&C+Sna+Mc 2015, Tennessee, Usa, April 19-23, 2015


Peak Cladding Temperature Prediction And Assessment For The Leibstadt Npp Using Simulate-3k
D. Chionis, K. Hofer, A.Pautz
Proc. American Nucl. Societ Student Conference 2015, College Station, Tx Texas A&M University, April 9-11, 2015


Enhancement And Validation Of Bwr Mcnp Activation Simulations For Swiss Decommissioning Planning
V. Bykov
Proc. American Nucl. Societ Student Conference 2015, College Station, Tx Texas A&M University, April 9-11, 2015

2014

Assessment Of Trace Against Single-Tube Post-Dryout Heat Transfer Experiments
Y. Aounallah
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014


Post-Test Analysis Of Oecd/Nea Rosa-2 Test 4 Using Trace
I. Clifford, O. Zerkak, A. Pautz
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014


Uncertainty And Sensitivity Analysis Of Cobra-Tf For The Simulation Of Selected Oecd/Nrc Bfbt Void Experiments
A. Epiney, O. Zerkak, A. Pautz
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014


Assessment Of Cfd Urans Models For Buoyancy Driven Mixing Flows Based On Rocom Experiments
R. Puragliesi, O. Zerkak And A. Pautz
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014


Treatment Of Epistemic And Aleatory Uncertainties In Det Simulations: Computational Framework With Ads-Trace
S. Rahman, D.R. Karanki, O. Zerkak, V.N. Dang
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014


Exploring Variability In Reflood Simulation Results: An Application Of Functional Data Analysis
D. Wicaksono,O. Zerkak, A. Pautz
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014


Sensitivity Analysis Of A Bottom Reflood Simulation Using The Morris Screening Method
D. Wicaksono,O. Zerkak, A. Pautz
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014


Analysis Of The Oecd/Nea Oskarshamn-2 Feedwater Transient And Stability Benchmark With Simulate-3k
A. Dokhane, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014


Uncertainty And Sensitivity Study Of Fuel Thermal Behaviour Within Oecd/Nea Uam Programme
Y. Yun, C. Cozzo, O. Leray, H. Ferroukhi
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014


Nuss-Rf: Stochastic Sampling-Based Tool For Nuclear Data Sensitivity And Uncertainty Quantification
T. Zhu, A. Vasiliev, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014


Stochastic Sampling-Based Tool For Nuclear Data Sensitivity Uncertainty Quantification
T. Zhu, A. Vasiliev, H. Ferroukhi, A. Pautz
Proc. Int. Youth. Nucl. Congress Iync2014, Burgos, Spain, July 6-12, 2014


Uncertainty Quantification Of Spent Fuel Nuclide Compositions Due To Cross-Sections, Decay Constants And Fission Yields
O. Leray, P. Grimm, M. Hursin, H. Ferroukhi And A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014


Quantification Of Code. Library And Cross-Section Uncertainty Effects On The Void Reactivity Coefficient Of A Bwr Uo2 Assembly
O. Leray, P. Grimm, H. Ferroukhi, And A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014


Effects Of Advanced Radial Submeshing Methods On Pin Power Reconstruction For An Epr Core Design
P. Mala, S. Canepa, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014


New Psi Methodology For Manufacturing And Technological Uncertainty Quantification
M. Pecchia, A. Vasiliev, O. Leray, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014


Updated Validation Of The Psi Criticality Safety Evaluation Methodology Using Mcnpx2.7 And Endf/B-Vii.1
M. Pecchia, A. Vasiliev, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014


Validation Of Two Monte Carlo Codes For Lwr Burnup Calculations
D. Wicaksono, P. Grimm, A.Vasiliev, M. Hursin, G. Perret, And H. Ferroukhi
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014


Analysis Of Axial Fuel Relocation Based On Gamma Scan Data From Oecd Halden Reactor Project Loca Tests
V. Brankov, G. Khvostov, K. Mikityuk, A.Pautz
Proc. Water Reactor Fuel Performance Meeting Wrfpm2014, Sendai, Japan, September 14-17, 2014


Fuel Relocation In Ifa-650 Loca Tests Based On Gamma Scan Data
V. Brankov, G. Khvostov, K. Mikityuk, A.Pautz
Proc. Enlarged Halden Project Group Meeting, Roeso, Norway, September 7-12, 2014


Reactivity Benchmark Analysis And Code Reactivity Prediction For A Pwr Fuel Assembly
H. Perrier, O. Leray, M. Pecchia, A. Vasiliev, H. Ferroukhi, A. Pautz
American Nuclear Society 2014 Student Conference, Psu, Pennsylvania, Usa, April 3-5, 2013


Neutronic Data Generation For Bwr Models, Comparison Of Serpent And Casmo-5
L. Rossinelli, M. Hursin. H. Ferroukhi, A. Pautz
American Nuclear Society 2014 Student Conference, Psu, Pennsylvania, Usa, April 3-5, 2013


Validation Enhancements Of The Psi Fast Neutron Fluence Computational Scheme Using Operational Pwr Experimental Data
A. Dupre, A. Vasiliev, H. Ferroukhi, A. Pautz
American Nuclear Society 2014 Student Conference, Psu, Pennsylvania, Usa, April 3-5, 2013

2013

Analysis Of A Halden Loca Test With The Bwr High Burnup Fuel
G. Khvotsov, A. Pautz, E. Kolstad, G. Ledergerber
Proc. Lwr Fuel Performance Meeting - **Top Fuel 2013, Charlotte, Usa, September 15-19, 2013


Investigation Of The Influence Of Off-Stoichiometry On The Radiation Damage Evolution In Uranium Dioxide
R. Ngayam-Happy, M. Krack
Proc. European Material Research Socitey Meeting E-Mrs 2013, Strasbourg, France, May 27-31, 2013


Thermal-Hydraulic System Code Performance For Sbloca Phenomonelogy Using Different Geometries And Scales
J. Freixa, S. Belaid, O. Zerkak
Proc. Nuclear Reactor Thermal-Hydraulics Nureth-15, Pisa, Italy, May 12-17, 2013


Post-Analysis Of A Turbine Trip Test At A Bwr/6 Using The Trace/S3k Coupled Code
K. Nikitin, T. Gudmunsson, S. Canepa, O. Zerkak, H. Ferroukhi, A. Pautz
Proc. Nuclear Reactor Thermal-Hydraulics Nureth-15, Pisa, Italy, May 12-17, 2013


Implementation And Validation Of A Condensation Heat Transfer Model For Slightly Inclined Horizontal Pipes For Relap5
R. Szijarto, J. Freixa, H.M. Prasser
Proc. Nuclear Reactor Thermal-Hydraulics Nureth-15, Pisa, Italy, May 12-17, 2013


Simulation Of International Standard Problem Isp-42 Phase B Using In-House Coupled Code Gothic-Trace
C. Adamsson, D. Papini, O. Zerkak And H.M. Prasser
Proc. Nuclear Reactor Thermal-Hydraulics Nureth-15, Pisa, Italy, May 12-17, 2013


Simulation Of International Standard Problem Isp-42 Phase B Using The Containment Code Gothic
D. Papini, C. Adamsson, M. Andreani And H.M. Prasser
Proc. Nuclear Reactor Thermal-Hydraulics Nureth-15, Pisa, Italy, May 12-17, 2013


On Bwr Regional Oscillations With Rotational Symmetry Line Using Simulate-3k
A. Dokhane, H. Ferroukhi, A. Pautz
Proc. Mathematics And Computations M&C 2013, Sun Valley, Usa, May 5-9, 2013


Application Of Power Time-Projection On The Operator Splitting Coupling Scheme Of The Trace/S3k Coupled Code
D. Wicaksono, O. Zerkak, K. Nikitin, H. Ferroukhi, A. Pautz
Proc. Mathematics And Computations M&C 2013, Sun Valley, Usa, May 5-9, 2013


Comparision Of Serpent And Casmo-5m For Pressurized Water Reactors Models
M. Hursin, A. Vasiliev, H. Ferroukhi, A. Pautz
Proc. Mathematics And Computations M&C 2013, Sun Valley, Usa, May 5-9, 2013


Preparation Of Nuclear Libraries With Deterministic And Stochastic Methods For Lwr Reflectors
S. Canepa, M. Hursin, H. Ferroukhi, A. Pautz
Proc. Mathematics And Computations M&C 2013, Sun Valley, Usa, May 5-9, 2013


Convergence Studies Of Deterministic Methods For Lwr Explicit Reflector Methodology
S. Canepa, M. Hursin, H. Ferroukhi, A. Pautz
Proc. Mathematics And Computations M&C 2013, Sun Valley, Usa, May 5-9, 2013


Comparison Of U.S Nrc Parcs Against Studsvik Simulate-3 Core Simulator For Modeling And Analysis Of Swiss Pwrs
S. Bogetic, M. Hursin, A. Dokhane, H. Ferroukhi, S. Canepa, A. Pautz
Proc. America Nuclear Society 2013 Student Conference, Mit, Boston, April 4-6, 2013


Study Of Nuclear Decay Data Contribution To Uncertainties In Heat Load Estimations For Spent Fuel Pools
H. Ferroukhi, O. Leray, M. Hursin, A. Vasiliev, G. Perret, A. Pautz
Proc. Nuclear Data Conference Nd2013, New York City, Usa, March 4-8, 2013


Nuclear Data Library E Ects On Fast To Thermal Flux Shapes Around Pwr Control Rod Tips
A. Vasiliev, H. Ferroukhi, T. Zhu, A. Pautz
Proc. Nuclear Data Conference Nd2013, New York City, Usa, March 4-8, 2013


Application Of The Psi-Nuss Tool For The Estimation Of Nuclear Data Related K-Eff Uncertainties For The Oecd/Nea Wpncs Uacsa Phase I Benchmark
T. Zhu, A. Vasiliev, H. Ferroukhi, A. Pautz
Proc. Nuclear Data Conference Nd2013, New York City, Usa, March 4-8, 2013


Comparison Of Two Approaches For Nuclear Data Uncertainty Propagation In Mcnp(X) For Selected Fast Spectrum Critical Benchmarks
T. Zhu, D. Rochman, A. Vasiliev, H. Ferroukhi, W. Wieselquist, A. Pautz
Proc. Nuclear Data Conference Nd2013, New York City, Usa, March 4-8, 2013


Multi-Scale Approach To Advanced Fuel Modelling For Enhanced Safety
F. Ribeiro, G. Khvostov
Proc. Eurosafe Meeting, Cologne, Germany, November 4-5, 2013 <


Deposition Of Inertial Drops In Eulerian Formulation
D. Caraghiaur, C. Adamsson, H. Anglart
Proc. Nureth-15, Pisa, Italy, May 12-17, 2013
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