Every year, several important international and national conferences and meetings take place. Our scientists, post docs and students are regularly invited to take part, write a conference paper and have presentations.
Please find here a selection of conferences:
- PHYSOR - International Conference on Physics of Reactors
- NURETH - International Topical Meeting on Nuclear Reactor Thermalhydraulics
- M&C - International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering
- ICONE - International Conference of Nuclear Engineering
- TOP FUEL - Light Wather Reactor Fuel Performance Conference
- ANS Student Conference
- ND - International conference on nuclear data for science and technology
2025
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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
2024
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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: 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 -
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 -
Vasiliev A, Lee H, Frankl M, Hursin M, Ferroukhi H
On the PSI routine criticality safety evaluation methodology and its validation approach
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 -
Vasiliev A, Ferroukhi H, Pecchia M, Rochman D, Laureau A, Lamirand V, et al.
Revision of PSI calculation capabilities and validation experience on the BEPU-type reactor dosimetry applications
In: Frajtag P, Thornton D, Wagemans J, eds. ISRD 17 – International symposium on reactor dosimetry (Part II). Vol. 308. EPJ web of conferences. Les Ulis: Edp sciences; 2024:03011 (11 pp.). https://doi.org/10.1051/epjconf/202430803011
DORA PSI -
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.
DORA PSI -
Verma L, Clifford I, Ferroukhi H, Scolaro A
Extending the validation database of Offbeat fuel performance code for Loca scenarios
In: Proceedings of TopFuel 2024 reactor fuel performance conference. European Nuclear Society (ENS); 2024:(10 pp.).
DORA PSI
2023
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Al-Yahia OS, Bernard M, Clifford I, Perret G, Bajorek S, Ferroukhi H
Implementation of a three-field framework in TRACE to improve the prediction of reactor core reflood conditions part II
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:110-122. https://doi.org/10.13182/NURETH20-40133
DORA PSI -
Alcayne V, Cano-Ott D, Garcia J, González-Romero E, Martínez T, Mendoza E, et al.
A segmented total energy detector (sTED) for (n, γ) cross section measurements at n_TOF EAR2
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/202328401043
DORA PSI -
Alcayne V, Mendoza E, Cano-Ott D, Kimura A, Aberle O, Amaducci S, et al.
Results of the 244Cm, 246Cm and 248Cm neutron-induced capture cross sections measurements at EAR1 and EAR2 of the n_TOF facility
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; 2023:01009 (6 pp.). https://doi.org/10.1051/epjconf/202328401009
DORA PSI -
Babiano-Suarez V, Balibrea-Correa J, Caballero-Ontanaya L, Domingo-Pardo C, Ladarescu I, Lerendegui-Marco J, et al.
High resolution 80Se(n,γ) cross section measurement 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; 2023:01001 (6 pp.). https://doi.org/10.1051/epjconf/202328401001
DORA PSI -
Cabellos O, Hursin M, Palmiotti P
WPEC/SG46 exercise on target accuracy requirement
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; 2023:14012 (4 pp.). https://doi.org/10.1051/epjconf/202328414012
DORA PSI -
Clifford I, Kral P, Vyskocil L, Pistora V, Trewin R, Filonova Y, et al.
State of the art for thermal-hydraulic analysis of pressurised thermal shock scenarios
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:5778-5790. https://doi.org/10.13182/NURETH20-40247
DORA PSI -
Clifford I, Al-Yahia OS, Ferroukhi H
TRACE investigation on the performance of passive safety condenser as ultimate heat sink
In: Proceedings of Saudi international conference on nuclear power engineering (SCOPE). sine loco: SCOPE; 2023:23220 (6 pp.).
DORA PSI -
Domingo-Pardo C, Babiano-Suarez V, Balibrea-Correa J, Caballero L, Ladarescu I, Lerendegui-Marco J, et al.
Compton imaging for enhanced sensitivity (n,γ) cross section TOF experiments: status and prospects
In: Mattoon CM, Vogt R, Escher J, Thompson I, Žugec P, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:01018 (5 pp.). https://doi.org/10.1051/epjconf/202328401018
DORA PSI -
Domingo-Pardo C, Aberle O, Alcayne V, Altieri S, Amaducci S, Andrzejewski J, et al.
The neutron time-of-flight facility n_TOF at CERN: recent facility upgrades and detector developments
In: 28th international nuclear physics conference (INPC 2022). Vol. 2586. Journal of physics: conference series. Bristol: IOP Publishing; 2023:012150 (11 pp.). https://doi.org/10.1088/1742-6596/2586/1/012150
DORA PSI -
Dupont E, Otuka N, Rochman D, Nogèure G, Aberle O, Alcayne V, et al.
Overview of the dissemination of n_TOF experimental data and resonance parameters
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; 2023:18001 (4 pp.). https://doi.org/10.1051/epjconf/202328418001
DORA PSI -
Fogliatto E, Clifford I
CFD simulations of the UPTF-TRAM test C1
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:606-617. https://doi.org/10.13182/NURETH20-40211
DORA PSI -
Freixa J, Martínez-Quiroga V, Perret G
Assessment of the choked flow model of RELAP5 for the application of inverse quantification methods
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:5426-5439. https://doi.org/10.13182/NURETH20-40674
DORA PSI -
García-Infantes ME, Praena P, Casanovas P, Mastromarco M, Aberle M, Alcayne M, et al.
First high resolution measurement of neutron capture resonances in 176Yb at the n_TOF CERN facility
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; 2023:09001 (5 pp.). https://doi.org/10.1051/epjconf/202328409001
DORA PSI -
Lerendegui-Marco J, Casanovas A, Alcayne V, Aberle O, Altieri S, Amaducci S, et al.
New perspectives for neutron capture measurements in the upgraded CERN-n_TOF Facility
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; 2023:01028 (6 pp.). https://doi.org/10.1051/epjconf/202328401028
DORA PSI -
Manna A, Pirovano E, Colonna N, Castelluccio D, Console Camprini P, Cosentino L, et al.
Characterization of a detector setup for the measurement of the 235U(n,f) cross section relative to n-p scattering up to 500 MeV at the n_TOF facility at CERN
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; 2023:04016 (5 pp.). https://doi.org/10.1051/epjconf/202328404016
DORA PSI -
Massimi C, Aberle O, Alcayne V, Altieri S, Amaducci S, Andrzejewski J, et al.
Neutron-induced cross section measurements
In: Freeman S, Lederer-Woods C, Manna A, Mengoni A, eds. Nuclear physics in astrophysics – X (NPA-X 2022). Vol. 279. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:11009 (6 pp.). https://doi.org/10.1051/epjconf/202327911009
DORA PSI -
Massimi C, Aberle O, Alcayne V, Altieri S, Amaducci S, Andrzejewski J, et al.
Nuclear astrophysics at n_TOF: focus on neutron sources in stars
In: Nicolis N, Papachristodoulou C, Patronis N, Stamoulis K, eds. Annual symposium of the Hellenic nuclear physics society. Vol. 29. HNPS advances in nuclear physics. Athens: National Documentation Centre; 2023:8-12. https://doi.org/10.12681/hnpsanp.5092
DORA PSI -
Mastromarco M, Manna A, García-Infantes F, Amaducci S, Mengoni A, Massimi C, et al.
Measurement of the 160Gd(n, γ) cross section at n_TOF and its medical implications
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; 2023:09002 (5 pp.). https://doi.org/10.1051/epjconf/202328409002
DORA PSI -
Michalopoulou V, Diakaki M, Vlastou R, Kokkoris M, Stamatopoulos A, Tsinganis A, et al.
Measurement of the 235U(n,f) cross section relative to the 10B(n,α) reaction with micromegas detectors at the CERN n_TOF facility: first results
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; 2023:01030 (4 pp.). https://doi.org/10.1051/epjconf/202328401030
DORA PSI -
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
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; 2023:01031 (4 pp.). https://doi.org/10.1051/epjconf/202328401031
DORA PSI -
Nikitin K, Arnold B, Clifford I, Ferroukhi H
Application of CTF subchannel code for BWR reload licensing analysis support
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:5569-5578. https://doi.org/10.13182/NURETH20-40978
DORA PSI -
Oprea A, Gunsing F, Schillebeeckx P, Aberle O, Bacak M, Berthoumieux E, et al.
Measurement of the 241Am(n,γ) cross section at the n_TOF facility at CERN
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; 2023:01036 (4 pp.). https://doi.org/10.1051/epjconf/202328401036
DORA PSI -
Pavón-Rodríguez JA, Alcayne V, Amaducci S, Bacak M, Casanovas A, Cortés-Giraldo MA, et al.
Characterisation of the n_TOF 20 m beam line at CERN with the new spallation target
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; 2023:06006 (6 pp.). https://doi.org/10.1051/epjconf/202328406006
DORA PSI -
Pirovano V, Manna D, Colonna J, Console Camprini E, Cosentino T, Dietz E, et al.
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
DORA PSI -
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
DORA PSI -
Rochman DA, Koning A, Goriely S
Covariances from model variation: application to quantities for astrophysics
In: Chiba G, Iwamoto O, eds. 5th international workshop on nuclear data covariances (CW2022). Vol. 281. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:00005 (6 pp.). https://doi.org/10.1051/epjconf/202328100005
DORA PSI -
Stamati ME, Torres-Sánchez P, Pérez-Maroto P, Cecchetto M, Goula M, Mastromarco M, et al.
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
DORA PSI -
Trewin R, Prošek A, Kral P, Clifford I, Perret G, Hartung J, et al.
Evaluation of uncertainties in thermal-hydraulic analyses of PTS for the APAL European project
In: Proceedings of the 20th international topical meeting on nuclear reactor thermal hydraulics. Downers Grove: American Nuclear Society; 2023:5791-5805. https://doi.org/10.13182/NURETH20-40288
DORA PSI
2022
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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.
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
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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/.
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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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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
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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.).
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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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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.
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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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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
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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
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
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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
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Hursin M, Pakari O, Perret G, Frajtag P, Lamirand V, Pázsit I, et al.
Validation of axial void profile measured by neutron noise techniques in crocus
In: 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
-
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
2019
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Alcayne V, Kimura A, Mendoza E, Cano-Ott D, Aberle O, Amaducci S, et al.
Measurement of the 244Cm and 246Cm neutron-induced cross sections at the n_TOF facility
In: García-Ramos J-E, Andrés MV, Pérez-Bernal F, Valera JA, Moro AM, eds. Basic concepts in nuclear physics: theory, experiments and applications. 2018 La Rábida international scientific meeting on nuclear physics. Vol. 225. Springer proceedings in physics. Cham: Springer; 2019:117-122. https://doi.org/10.1007/978-3-030-22204-8_4
DORA PSI -
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
DORA PSI -
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
DORA PSI -
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.
DORA PSI -
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.
DORA PSI -
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.
DORA PSI -
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.
DORA PSI -
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.
DORA PSI -
Hursin M, Pakari O, Perret G, Frajtag P, Lamirand V, Pázsit I, et al.
Measurement of the gas velocity in a water-air mixture in crocus by neutron noise technique
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.).
DORA PSI -
Hursin M, Park J, Kim W, Siefman D, Perret G, Vasiliev A, et al.
Uncertainty quantification of LWR-proteus phase II experiments using CASMO-5
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.).
DORA PSI -
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
DORA PSI -
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
DORA PSI -
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.
DORA PSI -
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
DORA PSI -
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
DORA PSI -
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.
DORA PSI -
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
DORA PSI -
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.
DORA PSI -
Papadionysiou M, Seongchan K, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
Assessment of nTRACER and parcs performance for VVER configurations
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.
DORA PSI -
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.
DORA PSI -
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.
DORA PSI -
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.
DORA PSI -
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
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
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
-
Cabellos O, Alvarez-Velarde F, Angelone M, Diez CJ, Dyrda J, Fiorito L, et al.
Benchmarking and validation activities within JEFF project
In: Siegler P, Mondelaers W, Plompen A, Hambsch F-J, Schillebeeckx P, Kopecky S, et al., eds. International conference on nuclear data for science and technology. Vol. 146. EPJ Web of Conferences. EDP Sciences; 2017:06004 (6 pp.). https://doi.org/10.1051/epjconf/201714606004
DORA PSI -
Chionis D, Dokhane A, Belblidia L, Pecchia M, Giardin G, Ferroukhi H, et al.
SIMULATE-3K analyses of neutron noise response to fuel assembly vibrations and thermal-hydraulics parameters fluctuations
In: Proceedings of the international conference on mathematics & computational methods applied to nuclear science & engineering (M&C 2017). Daejeon: Korean Nuclear Society; 2017:P289 (8 pp.).
DORA PSI -
Chollet M, Cozzo C, Bertsch J, Martin M, Grolimund D, Samson V-A
New insights in the fuel grain subdivision during in-plant irradiation up to high burn-up
Presented at: Water reactor fuel performance meeting 2017 (WRFPM 2017); September 10-14, 2017; Jeju, Korea.
DORA PSI -
Cozzo C, Bertsch J, Fave L, Rahman S, Dokhane A, Krack M, et al.
SiC cladding behavior: experiments and modelling at PSI
Presented at: Water reactor fuel performance meeting 2017 (WRFPM 2017); September 10-14, 2017; Jeju, Korea.
DORA PSI -
Curti E, Krack M, Grolimund D, Churakov SV
The chemical state of 79Se in spent nuclear fuel: Implications for the performance assessment
In: 16th international high-level radioactive waste management conference. Creating a safe and secure energy future for generations to come - driving toward long-term storage and disposal. American Nuclear Society; 2017:281-285.
DORA PSI -
Dokhane A, Grandi G, Leray O, Rochman D, Vasiliev A, Ferroukhi H
Nuclear data uncertainty decomposition for SPERT-III RIA experiments using SIMULATE-3K and SHARK-X
In: Proceedings of the international conference on mathematics & computational methods applied to nuclear science & engineering (M&C 2017). Daejeon: Korean Nuclear Society; 2017:P236 (8 pp.).
DORA PSI -
Fischer U, Avrigeanu M, Avrigeanu V, Cabellos O, Dzysiuk N, Koning A, et al.
Nuclear data for fusion technology - the European approach
In: Siegler P, Mondelaers W, Plompen A, Hambsch F-J, Schillebeeckx P, Kopecky S, et al., eds. International conference on nuclear data for science and technology. Vol. 146. EPJ Web of Conferences. EDP Sciences; 2017:09003 (6 pp.). https://doi.org/10.1051/epjconf/201714609003
DORA PSI -
Fischer U, Angelone M, Avrigeanu M, Avrigeanu V, Bachmann C, Dzysiuk N, et al.
The role of nuclear data for fusion nuclear technology
Presented at: International symposium on fusion nuclear technology; September 25-29, 2017; Kyoto, Japan.
DORA PSI -
Fleming M, Sublet J-C, Gilbert MR, Koning A, Rochman D
TALYS/TENDL verification and validation processes: Outcomes and recommendations
In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:02033 (4 pp.). https://doi.org/10.1051/epjconf/201714602033
DORA PSI -
Griffin P, Rochman D, Koning A
Characterization of the energy-dependent uncertainty and correlation in silicon neutron displacement damage metrics
In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:02008 (6 pp.). https://doi.org/10.1051/epjconf/201714602008
DORA PSI -
Herrero JJ, Rochman D, Leray O, Vasiliev A, Pecchia M, Ferroukhi H, et al.
Impact of nuclear data uncertainty on safety calculations for spent nuclear fuel geological disposal
In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:09028 (4 pp.). https://doi.org/10.1051/epjconf/201714609028
DORA PSI -
Hursin M, Leray O, Perret G, Pautz A, Bostelmann F, Aures A, et al.
Impact of implicit effects on uncertainties and sensitivities of the Doppler coefficient of a LWR pin cell
In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:09034 (5 pp.). https://doi.org/10.1051/epjconf/201714609034
DORA PSI -
Leray O, Rochman D, Fleming M, Sublet J-C, Koning A, Vasiliev A, et al.
Fission yield covariances for JEFF: a Bayesian Monte Carlo method
In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:09023 (4 pp.). https://doi.org/10.1051/epjconf/201714609023
DORA PSI -
Mala P, Pautz A, Canepa S, Ferroukhi H
Nodal and pin-by-pin calculations comparison with codes SIMULATE-5 and DYN3D
In: International conference on mathematics & computational methods applied to nuclear science & engineering (M&C 2017). Daejeon: Korean Nuclear Society; 2017:(9 pp.).
DORA PSI -
Mukin R, Clifford I, Ferroukhi H, Seidl M
Thermal hydraulic analysis of PWR assembly bowing using subchannel code COBRA-TF
Presented at: 17th international topical meeting on nuclear reactor thermal hydraulics (NURETH 2017); September 3-8, 2017; Xi'an, China.
DORA PSI -
Rochman D, Mala P, Ferroukhi H, Vasiliev A, Seidl M, Janin D, et al.
Bowing effects on power and burn-up distributions for simplified full PWR and BWR cores
In: Proceedings of the international conference on mathematics & computational methods applied to nuclear science & engineering (M&C 2017). Daejeon: Korean Nuclear Society; 2017:P286 (7 pp.).
DORA PSI -
Rochman D, Koning AJ, Sublet JC, Fleming M, Bauge E, Hilaire S, et al.
The TENDL library: hope, reality and future
In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:02006 (5 pp.). https://doi.org/10.1051/epjconf/201714602006
DORA PSI -
Siefman DJ, Hursin M, Grimm P, Pautz A
Case study of data assimilation methods with the LWR-Proteus Phase II experimental campaign
In: Proceedings of the international conference on mathematics & computational methods applied to nuclear science & engineering (M&C 2017). Daejeon: Korean Nuclear Society; 2017:(10 pp.).
DORA PSI -
Sjöstrand H, Conroy S, Helgesson P, Hernandez SA, Koning A, Pomp S, et al.
Propagation of nuclear data uncertainties for fusion power measurements
In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:02034 (4 pp.). https://doi.org/10.1051/epjconf/201714602034
DORA PSI
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
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
2016
-
Bocharov D, Krack M, Kalinko A, Purans J, Rocca F, Ali SE, et al.
Ab initio molecular dynamics simulations of the Sc K-edge EXAFS of scandium trifluoride
In: Grunwaldt J-D, Hagelstein M, Rothe J, eds. 16th international conference on X-ray absorption fine structure (XAFS16). Vol. 712. Journal of physics: conference series. Bristol, Philadelphia: IOP Publishing; 2016:012009 (4 pp.). https://doi.org/10.1088/1742-6596/712/1/012009
DORA PSI -
Bocharov D, Chollet M, Krack M, Bertsch J, Grolimund D, Martin M, et al.
Interpretation of the U L3-edge EXAFS in uranium dioxide using molecular dynamics and density functional theory simulations
In: 16th international conference on X-ray absorption fine structure (XAFS16). Vol. 712. Journal of physics: conference series. Bristol, Philadelphia: IOP Publishing; 2016:12091 (4 pp.). https://doi.org/10.1088/1742-6596/712/1/012091
DORA PSI -
Bykov V, Vasiliev A, Ferroukhi H, Pautz A
Solution of the BEAVRS benchmark using CASMO-5 / SIMULATE-5 code sequence
In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:1960-1968.
DORA PSI -
Canepa S, Ferroukhi H, Min R, Joo HG
Comparative study of CASMO-5/simulate-5 and nTRACER for EPR core analyses
In: International congress on advances in nuclear power plants, ICAPP 2016. Vol. 2. American Nuclear Society; 2016:1436-1445.
DORA PSI -
Chionis D, Dokhane A, Ferroukhi H, Pautz A
On causality analysis of nuclear reactor noise using partial directed coherence
In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:1162-1171.
DORA PSI -
Cozzo C, Epiney A, Canepa S, Ferroukhi H, Zerkak O, Khvostov G, et al.
Full core LOCA analysis for BWR/6 - methodology and first results
In: Top Fuel 2016. LWR fuels with enhanced safety and performance. LaGrange Park, IL, USA: American Nuclear Society; 2016:1135-1144.
DORA PSI -
Dokhane A, Leray O, Rochman D, Ferroukhi H, Pautz A, Grandi G
Validation of SIMULATE-3K against SPERT-III RIA experiments with quantification of nuclear data uncertainties
In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:3803-3812.
DORA PSI -
Grimm P, Hursin M, Perret G, Siefman D, Ferroukhi H
CASMO-5 analysis of reactivity worths of burnt PWR fuel samples measured in LWR-proteus PHASE II
In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:2518-2527.
DORA PSI -
Hursin M, Siefman D, Perret G, Grimm P, Pautz A
Verification of the new implementations in SHARK-X for reactivity coefficients and relative reactivity worth UQ
In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:674-683.
DORA PSI -
Leray O, Fiorito L, Rochman D, Ferroukhi H, Pautz A, Stankovskiy A, et al.
Comparison of fission yield perturbation methodologies on nuclide composition for a PWR UO2 fuel assembly
In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:1669-1680.
DORA PSI -
Li J, Rochman D, Herrero J, Ferrouki H, Vasiliev A, Pautz A
Towards analysis of the bowing effect on burnt nuclear fuel compositions using SERPENT
Presented at: American Nuclear Society 2016 student conference; March 31 - April 3, 2016; University of Wisconsin, Madison, USA.
DORA PSI -
Savelli R, Vasiliev A, Ferroukhi H, Pautz A
Extention of PSI FNF modeling methodology validation using BWR dosimetry data
Presented at: American Nuclear Society 2016 student conference; March 31 - April 3, 2016; University of Wisconsin, Madison, USA.
DORA PSI -
Sublet JC, Koning AJ, Rochman D, Fleming M, Gilbert M
TENDL-2015: Delivering both completeness and robustness
In: Advances in nuclear nonproliferation technology and policy conference (ANTPC 2016). Advances in nuclear nonproliferation technology and policy conference: bridging the gaps in nuclear nonproliferation, ANTPC 2016. American Nuclear Society; 2016:(4 pp.).
DORA PSI
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
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 PPSI 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
-
Brankov V, Khvostov G, Mikityuk K, Pautz A, Restani R, Abolhassani S, et al.
Modeling of axial distribution of released fission gas in KKL BWR fuel rods during base irradiation
In: TopFuel 2015. Reactor fuel performance. Conference proceedings. Part 1. Brussels: European Nuclear Society; 2015:609-619.
DORA PSI -
Bykov V, Volmert B, Pautz A
Enhancement and Validation of BWR MCNP Activation Simulations for Swiss Decommissioning Planning
Presented at: 2015 American Nuclear Society Student Conference; April 9-11, 2015; College Station, TX, USA.
DORA PSI -
Canepa S, Krack M, Ferroukhi H, Pautz A
Scalability benchmarking methodology for hybrid parallel core calculations with the code nTRACER
In: Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015). LaGrange Park, IL, USA: American Nuclear Society; 2015:2819-2831.
DORA PSI -
Chionis D, Hofer K, Pautz A
Peak cladding temperature prediction and assessment for the Leibstadt NPP using SIMULATE-3K
In: 2015 ANS student conference. Powering tomorrow together. La Grange Park: American Nuclear Society; 2015:(6 pp.).
DORA PSI -
Chollet M, Krsjak V, Cozzo C, Bertsch J
Positron annihilation spectroscopy study of lattice defects in non-irradiated doped and un-doped fuels
In: TopFuel 2015. Reactor fuel performance. Conference proceedings. Part 1. Brussels: European Nuclear Society; 2015:502-509.
DORA PSI -
Chollet M, Krack M, Kuzmin A, Bertsch J, Grolimund D, Martin M
Theoretical modelling of pristine and chromium-doped UO2
Presented at: E-MRS 2015; May 11-15, 2015; Lille, France.
DORA PSI -
Clifford I, Vasiliev A, Zerkak O, Ferroukhi H, Pautz A
Computational fluid dynamics analysis of the fluid flow and heat transfer in the core bypass region of a PWR
In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:7806-7819.
DORA PSI -
Dokhane A, Zerkak O, Ferroukhi H, Gajev I, Judd J, Kozlowski T
TRACE/SIMULATE-3K analysis of the NEA/OECD Oskarshamn-2 stability benchmark
In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:4757-4770.
DORA PSI -
Epiney A, Canepa S, Zerkak O, Ferroukhi H
Towards a consolidated approach for the validation of plant system codes and models: case study for a BWR fast depressurisation event
In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:2157-2170.
DORA PSI -
Herrero JJ, Pecchia M, Ferroukhi H, Canepa S, Vasiliev A, Caruso S
Computational scheme for burnup credit applied to long term waste disposal
In: ICNC 2015 - international conference on nuclear criticality safety. LaGrange Park, IL, USA: American Nuclear Society; 2015:1783-1791.
DORA PSI -
Hursin M, Rossinelli L, Ferroukhi H, Pautz A
BWR full core analysis with SERPENT/SIMULATE-3 hybrid stochastic/determinstic code sequence
In: Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015). LaGrange Park, IL, USA: American Nuclear Society; 2015:1794-1806.
DORA PSI -
Krepel J, Brankov V, Mikityuk K
Selection of initial fuel composition for the ESFR core based on the knowledge of its equilibrium closed cycle parameters
In: Track 8 - deployment and scenarios. Vienna: International Atomic Energy Agency; 2015:(9 pp.).
DORA PSI -
Kriventsev V, Rineiski A, Pfrang W, Perez-Martin S, Mikityuk K, Khvostov G
Benchmark on behavior of MOX fuel pin under irradiation at nominal power in sodium fast reactor
In: TopFuel 2015. Reactor fuel performance. Conference proceedings. Part 2. Brussels: European Nuclear Society; 2015:550-559.
DORA PSI -
Leray O, Pecchia M, Vasiliev A, Ferroukhi H, Pautz A, Perrier H
Development, verification and test application of a hybrid CASMO-5/SERPENT depletion scheme
In: Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015). LaGrange Park, IL, USA: American Nuclear Society; 2015:1781-1793.
DORA PSI -
Mala P, Canepa S, Ferroukhi H, Pautz A
Preparation of pin-by-pin nuclear libraries with superhomogenization method for nTRACER and DORT core calculations
In: Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015). LaGrange Park, IL, USA: American Nuclear Society; 2015:775-786.
DORA PSI -
Pecchia M, Herrero JJ, Ferroukhi H, Vasiliev A, Canepa S, Pautz A
COMPLINK: a versatile tool for automatizing the representation of material data in MCNP models
In: ICNC 2015 - international conference on nuclear criticality safety. LaGrange Park, IL, USA: American Nuclear Society; 2015:513-522.
DORA PSI -
Vasiliev A, Rochman D, Zhu T, Pecchia M, Ferroukhi H, Pautz A
Towards application of neutron cross-section uncertainty propagation capability in the criticality safety methodology
In: ICNC 2015 - international conference on nuclear criticality safety. LaGrange Park, IL, USA: American Nuclear Society; 2015:606-615.
DORA PSI -
Wicaksono D, Zerkak O, Pautz A
A methodology for global sensitivity analysis of transient code output applied to a reflood experiment model using TRACE
In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:4862-4879.
DORA PSI
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
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
2010-2014
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Betschart T, Suckow D, Brankov V, Prasser HM
The hydrodynamics of two-phase flow in a tube bundle and a bare channel
In: Vol. 2. International congress on advances in nuclear power plants (ICAPP 2014). American Nuclear Society; 2014:1403-1411.
DORA PSI -
Dokhane A, Ferroukhi H, Pautz A
Analysis of the OECD/NEA Oskarshamn-2 feedwater transient and stability benchmark with simulate-3K
In: Proceedings of the international conference on physics of reactors (PHYSOR 2014). PHYSOR 2014 – the role of reactor physics toward a sustainable future. ; 2014:1101708 (14 pp.).
DORA PSI -
Dupré A, Vasiliev A, Ferroukhi H, Pautz A
Validation enhancements of the PSI Fast Neutron Fluence computational scheme using operational PWR experimental data
Presented at: American Nuclear Society 2014 student conference; April 3-6, 2014; Pennsylvania.
DORA PSI -
Grimm P, Perret G, Ferroukhi H
CASMO-4E AND CASMO-5 analysis of the isotopic compositions of the LWR-PROTEUS phase II burnt PWR UO2 fuel samples
Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
DORA PSI -
Hursin M, Ferroukhi H, Pautz A
Neutronic Data Generation for BWR Models, Comparison OF SERPENT and CASMO-5
Presented at: ANS student conference 2014; April 3-6, 2014; University Park, PA, USA.
DORA PSI -
Hursin M, Scriven M, Perret G, Grimm P, Pautz A
Pinpower uncertainty quantification of LWR-PROTEUS phase III experiments
Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
DORA PSI -
Leray O, Grimm P, Ferroukhi H, Pautz A
Quantification of code, library and cross-section uncertainty effects on the void reactivity coefficient of a BWR UO2 assembly
Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
DORA PSI -
Leray O, Pecchia M, Vasiliev A, Ferroukhi H, Pautz A
Reactivity benchmark Analysis and Code Reactivity Prediction for a PWR Fuel Assembly
Presented at: ANS student conference 2014; April 3-6, 2014; University Park, PA, USA.
DORA PSI -
Leray O, Grimm P, Hursin M, Ferroukhi H, Pautz A
Uncertainty quantification of spent fuel nuclide compositions due to cross sections, decay constants and fission yields
Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
DORA PSI -
Mala P, Canepa S, Ferroukhi H, Pautz A
Effects of advanced radial submeshing methods on pin power reconstruction for an EPR core design
Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
DORA PSI -
Ngayam-Happy RA, Krack M
Radiation damage characterization in non-stoichiometric uranium dioxide by molecular dynamics simulations
In: Caruge D, Calvin C, Diop CM, Malvagi F, Trama J-C, eds. SNA and MC 2013 - joint international conference on supercomputing in nuclear applications and monte carlo. sine loco: EDP Sciences; 2014:01301 (2 pp.). https://doi.org/10.1051/snamc/201401301
DORA PSI -
Pecchia M, Vasiliev A, Ferroukhi H, Pautz A
Updated validation of the PSI criticality safety evaluation methodology using MCNPX2.7 and ENDF/B-VII.1
Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
DORA PSI -
Vasiliev A, Wieselquist W, Ferroukhi H, Canepa S, Heldt J, Ledergerber G
Validation studies of computational scheme for high-fidelity fluence estimations of the Swiss BWRs
In: Vol. 4. Progress in nuclear science and technology. Tokyo: Atomic Energy Society of Japan; 2014:99-103. https://doi.org/10.15669/pnst.4.99
DORA PSI -
Wicaksono D, Grimm P, Vasiliev A, Hursin M, Perret G, Ferroukhi H
Validation of two Monte Carlo codes for LWR burnup calculations
Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
DORA PSI -
Yun Y, Leray O, Ferroukhi H
Uncertainty and sensitivity analysis of OECD/NEA UAM fuel thermal behaviour benchmark using a Falcon/URANIE methodology
Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
DORA PSI
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
Uncertainty And Sensitivity Study Of Fuel Thermal Behaviour Within OECD/NEA UAM 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
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
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
2013
Hursin M, Vasiliev A, Ferroukhi H, Pautz A
Comparison of SERPENT and CASMO-5M for pressurized water reactors models
In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2013). Vol. 3. La Grange Park, IL, USA: American Nuclear Society; 2013:1565-1576. https://www.ans.org/store/item-700377/.
DORA PSI
Khvostov G, Pautz A, Kolstad E, Ledergerber G
Analysis of a Halden LOCA test with the BWR high burnup fuel
In: LWR fuel performance meeting. TopFuel 2013. LaGrange Park, IL, USA: American Nuclear Society (ANS); 2013:644-651.
DORA PSI
Nikitin K, Gudmundsson T, Canepa S, Zerkak O, Ferroukhi H, Pautz A
Post-analysis of a turbine trip test at a BWR/6 using the TRACE/S3K coupled code
Presented at: 15th international topical meeting on nuclear reactor thermal-hydraulics, NURETH-15; May 12-17, 2013; Pisa, Italy.
DORA PSI
Wicaksono D, Zerkak O, Nikitin K, Ferroukhi H, Chawla R
Application of power time-projection on the operator-splitting coupling scheme of the trace/S3K coupled code
In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2013). Vol. 3. La Grange Park, IL, USA: American Nuclear Society; 2013:1748-1760. https://www.ans.org/store/item-700377/.
DORA PSI
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
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
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
2012
Dokhane A, Canepa S, Ferroukhi H
Transition to CASMO-5M and SIMULATE-3K for Stability Analyses of the Swiss BWRs
Presented at: PHYSOR 2012: advances in reactor physics - linking research, industry, and education.
DORA PSI
Ferroukhi H, Vasiliev A, Dufresne A, Chawla R
Towards a reference numerical scheme using MCNPX for PWR control rod tip fluence estimations
In: PHYSOR 2012: advances in reactor physics. Vol. 1. La Grange Park, IL, USA: American Nuclear Society; 2012:401-417. https://www.ans.org/store/item-700371/.
DORA PSI
Grimm P, Perret G
Experimental validation of CASMO-4E and CASMO-5M for radial fission rate distributions in a westinghouse SVEA-96 Optima2 BWR fuel assembly
In: PHYSOR 2012: advances in reactor physics. Vol. 4. La Grange Park, IL, USA: American Nuclear Society; 2012:3410-3421. https://www.ans.org/store/item-700371/.
DORA PSI
Grimm P, Vasiliev A, Wieselquist W, Ferroukhi H, Ledergerber G
Reactor physics studies for assessment of tramp uranium methods
In: Advances in reactor physics. Vol. 2. LaGrange Park, IL, USA: American Nuclear Society; 2012:1522-1535.
DORA PSI
Krack M
Atomistic simulation of nuclear fuels
In: Vol. 1383. Materials Research Society Symposium Proceedings. ; 2012:19-25. https://doi.org/10.1557/opl.2012.520
DORA PSI
Wieselquist W, Vasiliev A, Ferroukhi H
Nuclear data uncertainty propagation in a lattice physics code using stochastic sampling
In: PHYSOR 2012: advances in reactor physics. Vol. 4. La Grange Park, IL, USA: American Nuclear Society; 2012:3000-3015. https://www.ans.org/store/item-700371/.
DORA PSI
Zhu T, Vasiliev A, Wieselquist W, Ferroukhi H
Stochastic sampling method with MCNPX for nuclear data uncertainty propagation in criticality safety applications
In: PHYSOR 2012: advances in reactor physics. Vol. 1. La Grange Park, IL, USA: American Nuclear Society; 2012:144-157. https://www.ans.org/store/item-700371/.
DORA PSI
Simulation Of International Standard Problem ISP-42, Phases A And B With The TRACE Code
C. Adamsson, D. Papini, O.Zerkak, H.M. Prasser
Proc. Int. Top.Mtg. Nuclear Thermal-Hydraulics, Operatio And Safety, Nuthos-9, Kaohsiung, China, September 9-13, 2012
Study Of Condensation Heat Transfer In Passive Safety Systems Using GOTHIC And TRACE Codes
D. Papini, C. Adamsson, M. Andreani, H.M. Prasser
Proc. Int. Top.Mtg. Nuclear Thermal-Hydraulics, Operatio And Safety, Nuthos-9, Kaohsiung, China, September 9-13, 2012
Simulation Of Complex Transient Flow Patterns In The ESBWR Passive Containment Cooling System
C. Adamsson, D. Papini, O.Zerkak, H.M. Prasser
Proc. Int. Top.Mtg. Nuclear Thermal-Hydraulics, Operatio And Safety, Nuthos-9, Kaohsiung, China, September 9-13, 2012
Performance Of Heat Transfer Models Of Thermal-Hydraulic System Codes At The Invert Edwards Pipe Experiment
R. Szijarto, J. Freixa, H.M. Prasser
Proc. Int. Top.Mtg. Nuclear Thermal-Hydraulics, Operatio And Safety, Nuthos-9, Kaohsiung, China, September 9-13, 2012
Validation Studies Of Computational Scheme For High-Fidelity Fluence Estimations Of The Swiss BWRs
A. Vasiliev, W. Wieselquist, H. Ferroukhi, S. Canepa, J. Heldt, G. Ledergerber
Proc. Int. Conf. On Radiation Protection And Shielding, Rpsd/Icrs-12, Nara, Japan, September 2-7, 2012
Evaluation Of The Fuel Rod Behaviour In A BWR Spent Fuel Pool Under Boil-Off Conditions
H. Ferroukhi, G. Khvostov, O. Zerkak, A. Vasiliev, M.A. Zimmermann
Proc. Int. Workshop On Nuclear Safety And Severe Accidents, Nussa, Peking, China, September 7-8, 2012
Validation Of Kenorest With LWR-Proteus Phase Ii Samples
M. Wagner, R. Kilger, A. Pautz, W. Zwermann, P.Grimm, A. Vasiliev, H. Ferroukhi
Proc. Jahrestagung Kerntechnik, May 22-24, 2012, Stuttgart, Germany, 2012
The Impact Of Dynamics On The MLOCA Accident Model - An Application Of Dynamic Event Trees
D.R. Karanki, V.N. Dang, T-W. Kim
Proc. 11th In. Probabilistic Safety Assesment / Annual European Safety And Reliability Conference (Psam11/Esrel2012)
2011
Khvostov G, Wiesenack W, Oberländer BC, Kolstad E, Ledergerber G, Zimmermann MA
Post-test analysis of the Halden LOCA experiment IFA-650.7 using the Falcon code
In: Proceedings of the enlarged Halden project group meeting, EHPG 2011. Halden, Norway: sine nomine; 2011:F2.2 (10 pp.).
DORA PSI
Khvostov G, Kolstad E, Ledergerber G, Zimmermann MA, Wiesenack W, Brémond O, et al.
Pre-calculation using the Falcon fuel behaviour code of the fuel rod design parameters and the test-conditions for a two-run Halden LOCA test with KKL BWR high-burnup fuel
In: Enlarged Halden programme group meeting. Proceedings of the fuel & materials sessions. Vol. HPR-374. Halden, Norway: Institutt for Energiteknikk; 2011:F2.7 (21 pp.).
DORA PSI
Khvostov G, Zimmermann MA, Lyon W, Pytel M
Towards advanced modeling of MPS-assisted cladding failure during power ramps using the FALCON code
Presented at: 2011 Water reactor fuel performance meeting/LWR/Top fuel; September 11-14, 2011; Chengdu, China.
DORA PSI
Yun Y, Khvostov G, Freixa J, Zimmermann MA
Analysis of fuel rod behaviour in a EPRTM during the base irradiation and LOCA-transient utilizing the FALCON code
In: Proceedings of the 2010 LWR fuel performance/top fuel/WRFPM. sine loco: American Nuclear Society; 2011:345-353.
DORA PSI
OECD/NEA Main Steam Line Break PWR Benchmark Simulation By TRACE/S3K Coupled Code
K. Nikitin, A. Manera, H. Ferroukhi, J. Judd, G.M. Grandi
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011
Post-Test Thermal-Hydraulic Analysis Of Two Intermediate LOCA Tests At The ROSA Facility Including Uncertainty Evaluation
J. Freixa, T-W. Kim, A. Manera
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011
Testing Of The Quicktest-Ultimate Algorithm To Solve The Dissolved Convection Equation During A Boron Dilution Test At The PKL Facility
J. Freixa, T-W. Kim, A. Manera
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011
Validation Of Star-CCM+ For Bouyancy Driven Mixing In A PWR Reactor Pressure Vessel
V. Petrov, A. Manera
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011
Analysis Of The Performance Of The Kerena Emergency Condenser
A. Manera, H.M. Prasser, S. Leyer
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011
Prediction Of Void Fraction In A Subchannel And Bundle Geometry With FLICA4 And TRACE
T-W. Kim, A. Manera
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011
Revisiting Temporal Accuracy In Neutronics/T-H Code Coupling Using The NURESIM LWR Simulation Platform
O. Zerkak, I. Gajev, A. Manera, T. Kozlowski, A. Gommlich, S. Zimmer, S. Kliem, N. Crouzet, M.A. Zimmermann
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011
Assessment Of MCNPX/CINDER For Burnup Calculations
E. Kolbe, P. Grimm, A. Vasiliev, H. Ferroukhi
Proc. Int. Conf. On Nuclear Criticality Icnc 2011, Edinburgh, Scotland, September 19-22, 2011
Criticality Safety Evaluation Of A Swiss Wet Storage Pool Including Limited Buc And Uncertainty Analysis
E. Kolbe, P. Grimm, A. Vasiliev, H. Ferroukhi
Proc. Int. Conf. On Nuclear Criticality Icnc 2011, Edinburgh, Scotland, September 19-22, 2011
Development And Test Validation Of A Computational Scheme For High-Fidelity Fluence Estimations Of The Swiss BWRs
A. Vasiliev, W. Wieselquist, H. Ferroukhi, S. Canepa
Proc. Int. Conf. On Mathematics And Computational Methods Applied To Nucl. Science And Engineering,(M&C2011), Rio De Janeiro, Brazil, May 8-12, 2011
A Trend Analysis Methodology For Enhanced Validation Of 3-D LWR Core Simulations
W. Wieselquist, H. Ferroukhi, K. Bernatowicz
Proc. Int. Conf. On Mathematics And Computational Methods Applied To Nucl. Science And Engineering,(M&C2011), Rio De Janeiro, Brazil, May 8-12, 2011
Towards An Uncertainty Quantification Methodology With CASMO-5
W. Wieselquist, A. Vasiliev, H. Ferroukhi
Proc. Int. Conf. On Mathematics And Computational Methods Applied To Nucl. Science And Engineering,(M&C2011), Rio De Janeiro, Brazil, May 8-12, 2011
Development And Validation Of A Coupled CFD/System-Code Tool
D. Bertolotto, A. Manera, R. Chawla
Proc. Int. Congress On Advances in Nuclear Power Plants (Icapp2011), Nice, France, May 2-5, 2011
Presentation Of The Multi-Physics Subproject Of The NURISP European Project
J. Jimenez,M.A. Zimmermann, O. Zerkak ,Ph. Emonot
Proc. Annual Meeting of The Spanish Nuclear Society 2011
VIPRE-W/MEFISTO-T - A Mechanistic Toll For Transient Predictions Of Dryout In BWRFuel
C. Adamsson, J-M. Le Corre,
Proc. Nureth-14, Toronto, Canada, September 25-30, 2011
Transient Void, Pressure Drop And Critical Power BFBT Benchmark Analysis And Results With VIPRE-W/MEFISTO-T
J-M. Le Corre, C. Adamsson, P. Alvarez
Proc. Nureth-14, Toronto, Canada, September 25-30, 2011
On A Best-Estimate Approach To Calculation Of Dryout Probability During BWR Transients
C. Adamsson, J-M. Le Corre,
Proc. Nureth-14, Toronto, Canada, September 25-30, 2011
Discted Dynamic Event Tree Analysis Of MLOCA Using ADS-TRACE
D.R. Karanki, V.N. Dang, T-W. Kim
Proc. Top. Meetg. On Probabilistic Safety Assessment And Analysis, Ans Psa2011, Wilimington, Us, March 13-17, 2011
2010
Yun Y, Khvostov G, Freixa J, Zimmermann MA
Analysis of fuel rod behaviour in a EPRTM during the base irradiation and LOCA-transient utilizing the FALCON code
In: Proceedings of the 2010 LWR fuel performance/top fuel/WRFPM. sine loco: American Nuclear Society; 2011:345-353.
DORA PSI
Khvostov G, Zimmermann MA, Ledergerber G
Parametric study of fuel rod behaviour during the RIA using the modified FALCON code
In: Nuclear fuel behaviour during reactivity initiated accidents. Workshop proceedings. sine loco: OECD; 2010:247-258.
DORA PSI
Quantitative Analysis Of Effect Of Power Uprate On Core Damage Frequency Of MBLOCA
T.W. Kim, V.N. Dang, M.A. Zimmermann, A. Manera
Proc. Int. Mtg. On Nucl. Thermal-Hydraulics, Operation And Safety Nuthos-8, Shanghai, China, October 10-14, 2010
Thermal-Hydraulic Analysis Of An Intermediate LOCA Test At The Rosa Facility Including Uncertainty Evaluation
J. Freixa, T-W. Kim, A. Manera
Proc. Int. Mtg. On Nucl. Thermal-Hydraulics, Operation And Safety Nuthos-8, Shanghai, China, October 10-14, 2010
Development And Validation Of A CFD Model For The EPR Pressure Vessel
V. Petrov, A. Manera
Proc. Int. Congress On Advances in Nuclear Power Plants (Icapp'10), San Diego, California, Usa, June 13-17, 2010
Set-Up Of A Validation Strategy For The Coupled Code CFX/TRACE In The Floris Facility With The Aid Of CFD Simulations
D. Bertolloto,
Proc. Int. Congress On Advances in Nuclear Power Plants (Icapp'10), San Diego, California, Usa, June 13-17, 2010
Coupled 3-D Neutronics/Thermal-Hydraulic Core Analysis Of A BWR Nuclear Heating Transient
H. Ferroukhi, K. Hofer
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010
Peach Bottom 2 Turbine Trip 2 Simulation By TRACE/S3K Coupled Code
K. Nikitin, J. Judd, G.M. Grandi, A. Manera, H. Ferroukhi
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010
Verification Of PWR In- And Ex- Vessel Neutron Fluence Calculations With MCNPX, Based On The H.B. Robinson-2 Dosimetry Benchmark
A. Vasiliev, R. Pittarello, H. Ferroukhi, E. Kolbe
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010
Assessment Of The Jeff-3.1.1 Neutron Data Library For CSE Of LWR Fuel Storage Pools
E. Kolbe, A. Vasiliev, H. Ferroukhi
Proc. Int. Conf. On Nuclear Data For Science And Technology, Nd2010, Jeju Island, Korea, 26-30 April, 2010
Comparison Of Neutron Data Libraries For The Analysis Of The H.B.Robinson-2 Pressure Vessel Benchmark With The MCNPX Code
A. Vasiliev, R. Pittarello, E. Kolbe, H. Ferroukhi
Proc. Int. Conf. On Nuclear Data For Science And Technology, Nd2010, Jeju Island, Korea, 26-30 April, 2010
Some Insights Into The Role Of Axial Gas Flow In Fuel Rod Behaviour During The LOCA Based On HRP Experiments And Results Of Calculation By FALCON Coupled With The FRELAX Model
G. Khvostov, M.A. Zimmermann, W. Wiesenack, G. Ledergerber
Proc. Enlarged Halden Group Meeting, Norway, 14-19 March 2010
Core-Shell Vs Rigid-Ion Model For The Study Of Point Defects In UO2
F. Devynck, M. Krack
Proc. Nuclear Materials 2010 Conference (Numath2010), Zkm, Karlsruhe, Germany, October 4-7, 2010
Benchmarking Of Transient Codes Against Cycle 19 Measurements At Leibstadt Nuclear Power Plant (KKL)
C. Aguirre, S. Opel, H. Ferroukhi, G. Grandi, L. Belblidia, M. Thunman, C. Rotander,B-G. Bergdahl, S. Baumgartner, G. Ledergerber
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010
OECD/NEA Expert Group On Uncertainty Analysis For Criticality Safety Assessment: Current Activities
T. Ivanova, F. Fernex, E. Kolbe, A. Vasiliev, G-S. Lee, S-W. Woo, D. Mennerdahl, Y. Nagaya, J-C. Neuber, A. Hoefer, B. Rearden, D. Mueller, Y. Rugama
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010
A Low-Order Quasidiffusion Discretization Via Linear-Continuous Finite-Elements On Unstructure Triangular Meshes
W. Wieselquist
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010
2005-2009
2009
Khvostov G
A dynamic model for fission gas release and gaseous swelling integrated into the FALCON fuel analysis and licensing code
In: Water reactor fuel performance meeting 2009: WRFPM top fuel 2009. Vol. 1. Paris: Societe Francaise d'Energie Nucleaire (SFEN); 2009:192-202.
DORA PSI
TRACE And RELAP5 Thermal-Hydraulic Analysis On Boron Dilution Tests At The PKL Facility
J. Freixa, A. Manera
Proc. 13th Int. **Topical. Meetg. On Nuclear Reactor Thermal Hydraulics Nureth-13, Kanazawa, Japan September 27-October 2, 2009
Effect Of Power Uprate On Exceedance Frequency During MBLOCA With Minimum Specifications For Success
T-W. Kim, A. Manera, M.A. Zimmermann, V.N. Dang
Proc. 13th Int. **Topical. Meetg. On Nuclear Reactor Thermal Hydraulics Nureth-13, Kanazawa, Japan September 27-October 2, 2009
Assessment Of S(Alpha,Beta) Libraries For Criticality Safety Evaluations Of Wet Storage Pools By Refined Trend Analyses
E. Kolbe, A. Vasiliev, H. Ferroukhi
Proc. Nuclear Criticality Safety Division **Topical Meeting Ncsd 2009, Richland, Washington, Us, September 13-17, 2009
A Dynamic Model For Fission Gas Release And Gaseous Swelling Integrated Into The FALCON Fuel Analysis And Licensing Code
G. Khvostov
Proc. **Top Fuel 2009, Paris, France, September 6-10, 2009
Towards Quantification Of Plant Safety Margins - A Status Report
M.A. Zimmermann, T-W. Kim, S. Laroche, A. Ui, S. Ebata, J-J. Jeong, H-G. Lim, S-H. Ahn, M. Gavrilas, J. Hortal
Proc. 13th Int. Topical. Meetg. On Nuclear Reactor Thermal Hydraulics Nureth-13, Kanazawa, Japan , September 27-October 2, 2009
Insights Into Fuel Rod Performance Codes During Ramps: Results Of A Code Benchmark Based On The Scip Project
L.E. Herranz, I. Vallejo, G. Khvostov, J. Sercombe, G. Zhou
Proc. of Top Fuel 2009, Paris, France, September 2009
A Quasidiffusion Method For Unstructured Quadrilateral Meshes In 2d XY Geometry
W.A. Wieselquist, D. Y. Anistratov
Proc. Int. Conf. On Mathematics, Computational Methods And Reactor Physics (Mc2009), Saratoga Springs, New York, May 3-7, 2009
2008
Khvostov G, Zimmermann MA, Stoenescu R, Ledergerber G
Definition of optimal parameters of fuel rod design and test conditions for the high temperature LOCA experiment IFA-650.7 using the FALCON fuel behaviour code
In: Proceedings of the fuels & materials sessions. Vol. HPR-369. Sine loco: Institutt for energiteknikk; 2008:(20 pp.).
DORA PSI
Khvostov G, Zimmermann MA, Sugiyama T, Fuketa T
On the use of the FALCON code for modeling the behaviour of high burn-up BWR fuel during the LS-1 pulse-irradiation test
In: Nuclear power: a sustainable resource: PHYSOR'08, International conference on the physics of reactors, 14-19 September 2008, Interlaken, Switzerland ; proceedings. Villigen: Paul Scherrer Institut PSI; 2008:1-8.
DORA PSI
Khvostov G, Zimmermann MA, Ledergerber G, Kolstad E, Montgomery RO
Parametric study of the behaviour of a pre-irradiated BWR fuel rod under conditions of LOCA simulated in the Halden in-pile test system with the FALCON code
In: Water reactor fuel performance meeting 2008. Daejeon, Korea; Tokyo, Japan: Korean Nuclear Society (KNS); Atomic Energy Society of Japan; 2008:8099 (10 pp.).
DORA PSI
Kolbe E, Vasiliev A, Zimmermann MA
Validation of standard neutron data libraries for LWR storage pools and transport casks criticality safety evaluations
In: ND 2007 - international conference on nuclear data for science and technology 2007. Les Ulis Cedex A, France: EDP Sciences; 2008:799-802. https://doi.org/10.1051/ndata:07441
DORA PSI
Vasiliev A, Ferroukhi H, Zimmermann MA, Kolbe E
On the observation of discrepancies in the 16O(n,α) data between different evaluated nuclear data files
In: ND 2007 - international conference on nuclear data for science and technology 2007. Les Ulis Cedex A, France: EDP Sciences; 2008:965-968. https://doi.org/10.1051/ndata:07445
DORA PSI
Single-Phase Mixing Studies By Means Of A Directly Coupled CFD/System-Code Tool
D. Bertolotto , A. Manera, B.L. Smith, H.M. Prasser, R. Chawla
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland (Cd-Rom,Fp412)
CFD Simulations Of A Single-Phase Mixing Experiment
D. Bertolotto , A. Manera, B.L. Smith, H.M. Prasser, R. Chawla
Proc.Int.Youth. Nuclear Congress Iync 2008 September 20-26, 2008, Interlaken, Switzerland
Estimation Of The Fast Neutron Fluence At Control Rod Tips Using A 3-D Diffusion/2-D Transport Calculation Scheme
H. Ferroukhi H., J-M. Hollard, M.A. Zimmermann, R. Chawla
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland
Core Modelling And Analysis Of The Swiss Nuclear Power Plants For Qualified R&D Applications
H. Ferroukhi , K. Hofer, J-M. Hollard, A. Vasiliev, M.A. Zimmermann
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland
Comparative Study Of CORETRAN And SIMULATE-3k For Main Steam Line Break Analyses
H. Ferroukhi , O. Zerkak, R. Chawla
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland
On The Use Of Importance Factors From Monte Carlo Calculations For Efficient Fast Neutron Fluence Prediction
A. Vasiliev, H. Ferroukhi, E. Kolbe, M.A. Zimmermann
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland
Propagation Of Void Fraction Uncertainty Measures In The RETRAN-3d Simulation Of The Peach Bottom Turbine Trip
P. Vinai, R. Macian-Juan, R. Chawla
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland (Fp607)
Effects Of The Core Inlet Mixing Modelling On A Main Steam Line Break Analysis At Hot Full Power
O. Zerkak, H. Ferroukhi
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland
Effect Of Longitudinal Pitch On The Heat Transfer Characteristics Of Aligned Tube Banks In Crossflow
T-W. Kim
Proc. Nuthos-7, 5-9 October 2008, Seoul, Korea
Code-To-Code Comparison For Blowdown Transients At Supercritical Conditions
A. Manera, O. Antoni
Proc. Jahrestagung Kerntechnik 2008, 27-29 May 2008, Hamburg, Germany
2007
Khvostov G, Romano A, Zimmermann MA
Modeling the effects of axial fuel relocation in the IFA-650.4 LOCA test
Presented at: Enlarged Halden programme group meeting 2007; March 11-16, 2007; Storefjell, Norway.
DORA PSI
Assessment Of The Capability Of The TRACE Code To Model Propagation Of Linear Acoustic Pressure Waves In One-Dimensional Flow
W. Barten, A. Manera, Juan. Macian,
Nureth-12, 30 September- 4 October 2007, Pittsburgh, Usa
PWR Cell Calculations Using Apollo-2 Within The Nuresim Benchmark Framework
H. Ferroukhi, J. Hollard, Zerkak. M, Coddington. O,
Trans.American.Nuclear.Society, Vol. 97, Pp 703-704 (2007)
Assessment Of The Chf Models In TRACE Code Against Rod Bundle Experimental Data
A. Jasiulevicius, Juan. Macian,
Icone-15, 22-26 April 2007, Nagoya, Japan
Simulation Of Rosa-V Test 6.2 Using TRACE V.4.274 Code
A. Jasiulevicius, O. Zerkak, Juan. Macian,
Icone-15, 22-26 April 2007, Nagoya, Japan
Assessment Of TRACE Film Condensation Models With And Without Non-Condensable Gases
A. Manera, Juan. Macian,
Nureth-12, 30 September - 4 October 2007, Pittsburgh, Usa
Lwr Multi-Physics Developments And Applications Within The Framework Of The Nuresim Europen Project
O. Zerkak, P. Coddington, N. Crouzet, E. Rover, J. Jimenez, D. Cuervo
Proc. Int. Top.Meetg. On Mathematics &Computation And Supercomputing in Nuclear Applications, M&C+Sna 2007, 15-19 April 2007, Monterey, Usa
Stability Effect Of The Lateral Lift Force In Homogeneous Bubbly Flow
D. Lucas, E. Krepper, H. Prasser, Manera. M,
Proc. Icmf2007, 9-13 July 2007, Leipzig, Germany
Comparison Between Wire-Mesh Sensor And Conductive Needle-Probes For Measurement Of Interfacial Area Densities
A. Manera, S. Paranjape, B. Ozar, M. Ishii, Hm. Prasser
Proc. Icone-15, 22-26 April 2007, Nagoya, Japan
Investigations On Mixing Phenomena In Single-Phase Flows In A T-Junction Geometry
R. Zboray, A. Manera, B. Niceno, Hm. Prasser
Proc. Nureth-12, 30 September - 4 October 2007, Pittsburgh, Usa, Cd-Rom
2006
Plaschy M, Destouches C, Chawla R, Beretz D, Mellier F, Servière H, et al.
Determination of adjusted neutron spectra in different MUSE configurations by unfolding techniques
In: Vehar DW, Gilliam DG, Adams JM, eds. Reactor dosimetry. 12th international symposium. Vol. 1490. West Conshohocken, PA: ASTM International; 2006:55-65. https://doi.org/10.1520/STP45426S
DORA PSI
Simulations Of The Halden IFA-650.3/.4 High Burnup LOCA Test With TRACE And FALCON: A Preliminary Study On Axial Relocation
Y. Aounallah, G. Khvostov, A. Romano, H. Wallin, M. Zimmermann, Kolstad. A, Ek. E, Kekkonen. M,
Int. Meeting On Lwr Fuel Performance (**Topfuel 2006), 22-26 October 2006, Salamanca, Spain
Analysis Of Umsicht Water Hammer Benchmark Tests: Results From PSI Using TRACE And RELAP5 Codes
W. Barten, A. Jasiulevicius, O. Zerkak, Juan. Macian,
7th Int. Conference On Hydroinformatics (Hic 2006), 4-8 September 2006, Nice, France, Vol. Ii, 1227-1234, 2006
Investigation Of Heat Transfer Mechanismus Under Shutdown Plant Conditions With TRACE v4. 160
A. Jasiulevicius, O. Zerkak, Juan. Macian,
Int. Congress On Advances in Nuclear Power Plants (Icapp'06), 4-8 June 2006, Reno, Usa, 1820-1828, 2006
Impact Of Different Correlation On TRACE v4.160 Predicted Critical Heat Flux
A. Jasiulevicius, Juan. Macian,
Int. Congress On Advances in Nuclear Power Plants (Icapp'06), 4-8 June 2006, Reno, Usa, 1820-1828, 2006
Predictions Of Critical Heat Flux In Annular Pipes With TRACE v4.160 Code
A. Jasiulevicius, Juan. Macian,
14th Int. Conference On Nuclear Engineering (Icone14),17-20 July 2006, Miami, Usa, 2006
Steady-State Film Boiling Heat Transfer Simulated With TRACE v4.160
A. Jasiulevicius, Juan. Macian,
14th Int. Conference On Nuclear Engineering (Icone14),17-20 July 2006, Miami, Usa, 2006
Assessment Of Standard Point-Wise Neutron Data Libraries For Criticality Safety Analysis With A Monte Carlo Code
E. Kolbe, A. Vasiliev, M. Zimmermann,
Proc. Physor-2006, 10-14 September 2006, Vancouver, Canada, 2006
CASMO-4/SIMULATE-3/MCNPX Analysis Of A Reactor Pressure Vessel Scraping Test
A. Vasiliev, H. Ferroukhi, M. Zimmermann,
Proc. Physor-2006, 10-14 September 2006, Vancouver, Canada, 2006
A Methodology For The Quantification Of Uncertainty In Best Estimate Code Physical Models
P. Vinai, Juan. Macian, Chawla. R,
Int. Congress On Advances in Nuclear Power Plants (Icapp'06), 4-8 June 2006, Reno, Usa, 1087-1098, 2006
2005
Mechanical Modeling Of Pressure Tube Tests Using The FEAT Code
W. Barten, A. Hermann, H. Wallin
Jahrestagung Kerntechnik 2005, 10-12 May 2005, Nuremberg, Germany, 2005
Assessment Of A BWR Analytical Reduced Order Model Against The System Code RAMONA: Applicability And Limitations
A. Dokhane, D. Hennig, Uddin. Rizwan, R. Chawla
Proc. 13th Int. Conference On Nuclear Engineering (Icone13), 16-20 May 2005, Beijing, China, 2005
A Reactor Noise Analysis Methodology For BWR Core Stability Evaluation: Application And Assessment To Leibstadt Stability Tests
A. Dokhane, H. Ferroukhi, M. Zimmermann, Aguirre. A,
Int. **Topical Meeting On Mathematics And Computation (M&C 2005), 12-15 September 2005, Avignon, France, 2005
Evaluation Of The PWR REA Pulse Width For Realistic Uo2/MOX Cores
H. Ferroukhi, M. Zimmermann,
Int. **Topical Meeting On Mathematics And Computation (M&C 2005), 12-15 September 2005, Avignon, France, 2005
Assessment Of TRACE Code Against CHF Experiments
A. Jasiulevicius, Juan. Macian, Coddington. R, Sanchez. P,
Proc. 11th Int. **Topical Meeting On Nuclear Reactor Thermal Hydraulics (Nureth-11), 2-6 October 2005, Avignon, France, 2005
Loss Of Residual Heat Removal System: Simulation By TRACEv4.00 Simulation Of A PKL Experiment
A. Jasiulevicius, O. Zerkak, Juan. Macian,
Trans.Am.Nuc.Soc., Volume 92, Pp 442-443, June 2005
CHF Experiments In Single Tubes TRACEv4.050 Code Validation
A. Jasiulevicius, Juan. Macian,
Trans.Am.Nuc.Soc., Volume 92, Pp 430-432, June 2005
Effect Of The Power Pulse Shape On The Fuel Thermal-Mechanical Response To RIAs: A Study Using FALCON And SCANAIR
A. Romano, M. Zimmermann,
Proc. Water Reactor Fuel Performance Meeting, Wrfpm05, 2-6 October 2005, Kyoto, Japan, 2005
Analysis Of MCNPX/JEF-2.2 And JENDL-3.3 Results For A Suite Of The Low-Enriched Thermal Compound Uranium Benchmarks
A. Vasiliev, J. Lebenhaft, M. Zimmermann,
Int. **Topical Meeting On Mathematics And Computation (M&C 2005), 12-15 September 2005, Avignon, France, 2005
Optimization Of UO2 Fueled PWR Core Design
E. Greenspan, F. Ganda, Z. Shayer, N. Todreas, J. Malen, C. Shuffler, J. Trant, A. Romano, B. Petrovic, H. Garkish
Proc. Int. Congress On Advances in Nuclear Power Plants, 15-19 May 2005, Seoul, Korea, 2005
2001-2004
2004
Boilling Suppression In Convective Flow
Y. Aounallah
Proc. Icapp04, 13-17 June 2004, Pittsburgh, Usa
RETRAN-3d Analysis Of The Extreme Cases Of Phase 3 Of The Peach Bottom 2 Turbine Trip Benchmark
W. Barten, P. Coddington
Jahrestagung Kerntechnik, 25-27 May 2004, DüSseldorf, Germany, Vol. Tagungsband, 3-8, 2004
Bifurcation Analysis Using The System Code RAMONA
A. Dokhane, D. Hennig, Uddin. Rizwan, R. Chawla
Proc. 12th Int. Conference On Nuclear Engineering (Icone 12), 25-29 April 2004, Arlington, Usa, 2004
Uncertainty Analysis Applied To Fuel Depletion Calculations
Macian-Juan R., Zimmermann M.A., Chawla R..
Physor 2004, 25-29 April 2004, Chicago, Usa, 2004
Assessment Of CASMO-4 Predictions Of The Iso**Topic Inventory Of High Burn-Up Mox Fuel
Macian-Juan R., Zimmermann M.A., Chawla R..
Physor 2004, 25-29 April 2004, Chicago, Usa, 2004
2003
Level-Swell Prediction With RETRAN-3d And Its Application To A BWR Steam Line Break Analysis
Y. Aounallah, K. Hofer
Proc. Int. Congress On Advanced Nuclear Power Plants (Icapp'03), 4-7 May 2003, CóRdoba, Spain
Peach Bottom BWR Turbine Trip Benchmark Phase 3: Analysis Of Full Plant System With 3d-Neutronics Using RETRAN-3d
W. Barten, P. Coddington
Proc. Mathematics & Computations 2003, 6-10 April 2003, Gatlinburg, Tennessee, Usa
Validation Of Monteburns For MOX Fuel Using ARIANE Experimental Results
J.R. Lebenhaft, H.R. Trellue
Proc. Mathematics & Computations 2003, 6-10 April 2003, Gatlinburg, Tennessee, Usa
Nuclear-Coupled Thermal-Hydraulic Nonlinear Stability Analysis Using A Novel BWR Reduced Order Model: Part 1 - The Effects Of Using Drift Flux Versus Homogeneous Equilibrium Models
A. Dokhane, D. Hennig, R. Chawla, Rizwan-Uddin
Proc. Icone11, 20-23 April 2003, Tokyo, Japan
Nuclear-Coupled Thermal-Hydraulic Nonlinear Stability Analysis Using A Novel BWR Reduced Order Model: Part 2 - Stability Limits Of In-Phase And Out-Of-Phase Modes
A. Dokhane, D. Hennig, R. Chawla, Rizwan-Uddin
Proc. Icone11, 20-23 April 2003, Tokyo, Japan
2002
Peach Bottom BWR Turbine Trip Benchmark: PSI Analysis Of Exercise 1 Using RETRAN-3d
W. Barten, P. Coddington, H. Ferroukhi
Proc. Physor 2002, 7-10 October 2002, Seoul, Korea
Stability And Bifurcation Analyses Of Two-Phase Flow Using A Drift Flux Model And Bifurcation Code Bifdd
A. Dokhane, D. Hennig, Uddin. Rizwan, R. Chawla
Proc. Tenth Int. Conference On Nuclear Engineering (Icone-10), 14-18 April 2002, Arlington, Virginia, Usa
A Parametric Study Of Heated Channels With Two-Phase Flow Using Bifurcation Analysis
A. Dokhane, D. Hennig, Uddin. Rizwan, R. Chawla
Proc. American Nuclear Society Annual Meeting, June 9-13, 2002, Florida, Usa, Trans. Ans, Vol. 86, 131-133 (2002)
Nonlinear Stability Analysis With A Novel BWR Reduced Order Model
A. Dokhane, D. Hennig, Uddin. Rizwan, R. Chawla
Proc. Physor 2002, 7-10 October 2002, Seoul, Korea
Transient 3-D Neutron Kinetic Analysis With CORETRAN Of A Core Thermal-Hydraulic Boundary Condition Model - Peach Bottom 2 Turbine Trip Benchmark Phase 2
H. Ferroukhi, W. Barten, P. Coddington
Proc. Physor 2002, 7-10 October 2002, Seoul, Korea
2001
Analysis And Sensitivity Studies With CORETRAN And RETRAN-3d Of The NEACRP Rod Ejection Benchmark
H. Ferroukhi, P. Coddington
Proc. Icone-9, Nice France, April 8-12, 2001.
Development Of A Model For RETRAN-3d For Pressure Losses At T-Junctions
W. Barten, P. Coddington, J. Sullivan
Proc. Icone-9, Nice France, April 8-12, 2001.
Analysis Of Different Hypothetical Recirculation Line SB-LOCAs In Kkm By TRAC-BF1/V98.1
G. Analytis, Coddington. Th,
Proc. Icone-9, Nice France, April 8-12, 2001.
Best Estimate Analysis Of The Thermal Expansion Scenario During Shutdown In A PWR
R. Macian, L. Nechvatal
Proc. Icone-9, Nice France, April 8-12, 2001.
CORETRAN/VIPRE Assembly Critical Power Assessment Against NUPEC BWR Experiments
Y. Aounallah
Proc. Icone-9, Nice, France, April 8-12, 2001.
RETRAN-3d Results And One-Dimensional Analytical Model For The Critical Power Of A Rod Bundle With Cosine-Shape Heating
W. Barten
Proc. Jahrestagung Kerntechnik 2001, Dresden, Germany, May 15-17, 2001.
Uncontrolled Rod Bank Withdrawal Benchmark Analysis With CORETRAN And RETRAN-3d
H. Ferroukhi, P. Coddington
Proc. Ans Int. Meeting On Mathematical Methods For Nuclear Applications, Mc-2001, Salt Lake City, September 2001.
Limited Burnup Credit For Increased Fuel Enrichments In A Swiss PWR Storage Pool
J-M. Parratte, P. Grimm
Proc. Ans **Topical Meeting On Practical Implementation of Nuclear Criticality Safety, Ncsd, Reno, Nevada, Usa, November 11-15, 2001
Some Remarks To Time Series Analysis For BWR Stability Analysis
B. Askari, K. Behringer, D. Hennig
Proc. Ans Int. Meeting On Mathematical Methods For Nuclear Applications, Mc-2001, Salt Lake City, September 2001.
2000 and before
Assessment Of RETRAN-3d Against Experimental Loss Of Coolant Scenarios
R. Macian, P. Coddington
Proc. Icone-8, Baltimore, Md, Usa 2000.
Assessment Of RETRAN-3d And VIPRE-02 Void Predictions Against Experimental Data
R. Macian, Y. Aounallah, P. Coddington P. Stangroom
Proc. Icone-8, Baltimore, Md, Usa 2000.
Towards A Best-Estimate Approach To A Steady-State And Transient Analysis Using The CORETRAN Code
H. Ferroukhi, P. Coddington, F. Holzgrewe
Proc. Int. Meeting On Best-Estimate Methods in Nuclear Installation Safety Analysis, Washington, Dc, Usa, Nov. 2000
Development And Assessment Of TRAC-BF1 For BWR Loca Applications
G. Th Analytis, P. Coddington
Proc. Int. Meeting On Best-Estimate Methods in Nuclear Installation Safety Analysis, Washington, Dc, Usa, Nov. 2000
Validation Of CASMO-4 Against Sims Measured Spatial Nuclide Distributions Inside A 9 WT% GD BWR Pin
F. Holzgrewe, Et Al.
Proc. Int. **Topical Meeting On Light Water Reactor Fuel Performance, Park City, Ut, Usa, April 2000.
Current And Future Applications Of Thermal-Hydraulic And Neutronic Best-Estimate Methods In Support Of The Swiss Licensing Process
M. A. Zimmermann, W. Van Doesburg
Proc. Csni/Oecd Workshop On Advanced Thermal-Hydraulic And Neutronic Codes: Current And Future Applications, Barcelona, Spain, April 10-13, 2000.
A Study Of The Performance Of Void Fraction Correlations Used In The Context Of Drift-Flux Two-Phase Flow Models
P. Coddington, R. Macian
Proc. Int. Meeting On Trends in Numerical And Physical Modelling For Industrial Multiphase Flows , Cargese, Corsica, September 27-29, 2000.
Remarks On Regional Power Oscillations In BWRs
D. Ginestar, D. Hennig, R. Miro, G. Verdu
Proc. Int. Conference On Mathematics And Computation, Reactor Physics And Environmental Analysis in Nuclear Applications, Madrid, Spain, Sept 27-30, 1999
Implementation Of An Improved Interfacial Mass And Energy Transfer Model In RETRAN- 3d
R. Macian, P. Cebull, P. Coddington, M. Paulsen
Proc. 9th Int. Meeting On Nuclear Reactor Thermal Hydraulics, Oct 4-8, 1999, San Francisco, Ca
VIPRE-02 Subchannel Validation Against NUPEC Void Fraction Data
Y. Aounallah, P. Coddington
Proc. 9th Int. Meeeting On Nuclear Reactor Thermal Hydraulics, Oct 4-8, 1999, San Francisco, Ca
Analysis Of Rod Bundle And Subchannel, Subcooled Boiling Experiments Using RETRAN-3d, TRAC-BF1 And VIPRE-02
P. Coddington, Y. Aounallah, D. Maier, D. Reedha
Proc. 9th Int. Meeting On Nuclear Reactor Thermal Hydraulics, Oct 4-8, 1999, San Francisco, Ca
The Physical Mechanism Of Core-Wide And Local Instabilities At The Forsmark-1 BWR
G. Th. Analytis, D. Hennig, J. K-H. Karlsson
Proc. 9th Int. Meeting On Nuclear Reactor Thermal Hydraulics, Oct 4-8, 1999, San Francisco, Ca
Assessment Of The Slip Options In RETRAN-3d Against A Wide Range Of Rod Bundle Void Data
D. Maier, P. Coddington
Proc. Icone6, 6th Int. Conference On Nuclear Engineering, May 10-15, 1998, San Diego, California, Usa
Einige Bemerkungen Zum Physikalischen Mechanismus Der Entstehung Von Oszillatorischen Instabilitäten In Siedewasserreaktoren
D. Hennig
Proc. Jahrestagung Kerntechnik Mai 1998, MüNchen.
Evaluation Of The Slip Options In RETRAN-3d
D. Maier, P. Coddington
Proc. 9th Int. Retran Meeting, June 7-10, 1998, Monterey, Ca, Usa
VIPRE-02 Subchannel Validation Against NUPEC BWR Void Fraction Data
Y. Aounallah, P. Coddington
Proc. 9th Int. Retran Meeting, June 7-10, 1998, Monterey, Ca, Usa
Implementation Of An Improved Interfacial Mass And Energy Transfer Model In RETRAN-3d
R. Macian, P. Cebull, P. Coddington, M. Paulsen
Proc. 9th Int. Retran Meeting, June 7-10, 1998, Monterey, Ca, Usa
BWR Stability Analysis At PSI
D. Hennig
Proc. Int. Conference On The Physics of Nuclear Science And Technology, Oct. 5 - 8, 1998, Long Island, New York
Evaluation Of The TRAC-BF1 Code Against BWR/6 Start-Up Tests
B. Brodbeck, P. Coddington
Proc. Icone5, Nice France, May 26-30, 1997, Paper No. 2461.
Review Of Wide Range Void Correlations Against An Extensive Database Of Rod Bundle Void Measurements
D. Maier, P. Coddington
Proc. Icone5, Nice, France, May 26-30, 1997, Paper No. 2434.
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