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Structure : Identifiant HAL de la structure : 580501

Impact of fission spectrum modeling on aging estimations of Pressurized Water Reactor vessels

Romain Vuiart , Patrizio Console Camprini , Kenneth W. Burn , Mariya Brovchenko , Julien Taforeau , et al.
2021 ANS Winter Meeting and Technology Expo, American Nuclear Society, Nov 2021, Washington, United States
Communication dans un congrès hal-03525466v1
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Development of a multi-zone fuel loading model for scenario studies involving ASTRID-like SFRs with the CLASS code

Léa Tillard , Jean-Baptiste Clavel , Xavier Doligez , Marc Ernoult
4th annual Technical Workshop on Fuel Cycle Simulation, TWOFCS19, Jun 2019, Urbana-Champaign, United States
Communication dans un congrès hal-04125741v1

New Capabilities of the MORET 6 Monte Carlo Neutron Transport Code

Wilfried Monange , Aurelie Bardelay
International Conference on Physics of Reactors 2022 (PHYSOR 2022), American Nuclear Society, May 2022, Pittsburgh, United States
Communication dans un congrès hal-04122140v1
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Contribution to the validation of the MORET 5 code using the CROCUS reactor physics benchmark

Nicolas Leclaire , Bertrand Cochet
Annals of Nuclear Energy, 2021, 155, pp.1-12. ⟨10.1016/j.anucene.2021.108164⟩
Article dans une revue hal-03202427v1
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Application of the SPH equivalence technique to the CABRI full core in non-fundamental mode

Alain Hébert , Julien Taforeau , Jean-Jacques Ingremeau
PHYSOR 2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear, American Nuclear Society, Mar 2020, Cambridge, United Kingdom. pp.03019, ⟨10.1051/epjconf/202124703019⟩
Communication dans un congrès irsn-04106635v1
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Nuclear Data Uncertainties and Adjustments Using Deterministic and Monte-Carlo Methods along with PWR Measurements

Vivian Salino , Dimitri Rochman , Eric Dumonteil , Fausto Malvagi , Alain Hébert
M&C 2023 - The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, American Nuclear Society, Aug 2023, Niagara Falls, Ontario, Canada
Communication dans un congrès irsn-04095487v2
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Neutronic Analysis of the European Sodium Fast Reactor: Part I—Fresh Core Results

Emil Fridman , Francisco Álvarez Velarde , Pablo Romojaro Otero , Haileyesus Tsige-Tamirat , Antonio Jiménez Carrascosa , et al.
Journal of Nuclear Engineering and Radiation Science, 2021, 8 (1), pp.11301. ⟨10.1115/1.4048905⟩
Article dans une revue irsn-04122162v3
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Generational Variance Reduction in Monte Carlo Criticality Simulations as a Way of Mitigating Unwanted Correlations

Kévin Fröhlicher , Eric Dumonteil , Loïc Thulliez , Julien Taforeau , Mariya Brovchenko
Nuclear Science and Engineering, 2023, pp.1-18. ⟨10.1080/00295639.2023.2193089⟩
Article dans une revue irsn-04122114v1
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A Detailed Analysis of the H.B. Robinson-2 Reactor Pressure Vessel Dosimetry Benchmark

Romain Vuiart , Mariya Brovchenko , Julien Taforeau , Eric Dumonteil
Energies, 2022, 15 (14), pp.5098. ⟨10.3390/en15145098⟩
Article dans une revue irsn-04122073v1
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Design Methodology for Fuel Debris Experiment in the New STACY Facility

Satoshi Gunji , Jean-Baptiste Clavel , Kotaro Tonoike , Isabelle Duhamel
ICNC 2019 - 11th International conference on Nuclear Criticality Safety, IRSN - Institut de Radioprotection et de Sûreté Nucléaire, Sep 2019, Paris, France
Communication dans un congrès hal-04125677v1
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Neutron spectrum unfolding using two architectures of convolutional neural networks

Maha Bouhadida , Asmae Mazzi , Mariya Brovchenko , Thibaut Vinchon , Mokhtar Z Alaya , et al.
Nuclear Engineering and Technology, 2023, 55 (6), pp.2276 - 2282. ⟨10.1016/j.net.2023.03.025⟩
Article dans une revue hal-04104489v1
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On the validation of VESTA 2.2.0 using the ARIANE-GU3 sample

Raphaelle Ichou , Benjamin Dechenaux
PHYSOR 2020, PHYSOR, Mar 2020, CAMBRIDGE, United Kingdom. pp.10005, ⟨10.1051/epjconf/202124710005⟩
Communication dans un congrès hal-03523803v1
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On the use of graph theory to interpret the output results from a Monte-Carlo depletion code

Benjamin Dechenaux
Journal of Nuclear Engineering and Radiation Science, 2021, 195 (5), pp.538-554. ⟨10.1080/00295639.2020.1847980⟩
Article dans une revue hal-03191108v1
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Global and flexible models for Sodium-cooled Fast Reactors in fuel cycle simulations

M. Ernoult , X. Doligez , Nicolas Thiollière , A.A. Zakari-Issoufou , A. Bidaud , et al.
Annals of Nuclear Energy, 2019, 128, pp.69-76. ⟨10.1016/j.anucene.2018.12.037⟩
Article dans une revue hal-01975524v1
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Neutronic Analysis of the European Sodium Fast Reactor: Part II - Burnup Results

Emil Fridman , Francisco Álvarez Velarde , Pablo Romojaro Otero , Haile Tsige-Tamirat , Antonio Jiménez Carrascosa , et al.
Journal of Nuclear Engineering and Radiation Science, 2021, 8 (1), pp.11302. ⟨10.1115/1.4048765⟩
Article dans une revue irsn-04122521v1
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Percolation properties of the neutron population in nuclear reactors

Benjamin Dechenaux , Thomas Delcambre , Eric Dumonteil
Physical Review E , 2022, 106 (6), pp.064126. ⟨10.1103/PhysRevE.106.064126⟩
Article dans une revue irsn-04122103v2

International criticality benchmark comparison exercise in support of nuclear data validation

William B. J. Marshall , Jenifer Alwin , David Heinrichs , Luiz Leal , Ellen Marie Saylor , et al.
15th International Conference on Nuclear Data for Science and Technology (ND2022), Jul 2022, Scramento (virtual evant), United States
Communication dans un congrès hal-03759208v1
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A Versatile Methodology for Reactor Pressure Vessel Aging Assessments

Romain Vuiart , Mariya Brovchenko , Julien Taforeau , Vaibhav Jaiswal , Eric Dumonteil
Nuclear Science and Engineering, 2022, 196 (4), pp.455-477. ⟨10.1080/00295639.2021.1991761⟩
Article dans une revue hal-03636003v1
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Investigating fission distribution behavior under various homogenization techniques for asymmetrical fuel assemblies and different reflector equivalence methods

Kevin Frohlicher , Vivian Salino , Alain Hebert
Annals of Nuclear Energy, 2021, 157, ⟨10.1016/j.anucene.2021.108221⟩
Article dans une revue hal-03207089v1
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PyNjoy2016: an Open Source System for Producing Cross Sections Libraries for DRAGON5 and SERPENT2

V. Salino , Alain Hébert
M&C 2023 - The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, American Nuclear Society, Aug 2023, Niagara Falls, Ontario, Canada
Communication dans un congrès irsn-04095482v2
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Impact du déploiement de réacteurs de type ASTRID sur la gestion dynamique du plutonium dans des scénarios de transitions électronucléaires

Léa Tillard
Physique Nucléaire Théorique [nucl-th]. Université Paris Saclay (COmUE), 2019. Français. ⟨NNT : 2019SACLS494⟩
Thèse tel-02628512v1
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Functional Expansion Tallies using Fission Matrix Eigenmodes for Full Core Criticality Simulations

Arnaud Repain , Fausto Malvagi
Annals of Nuclear Energy, 2023, 182, pp.109543. ⟨10.1016/j.anucene.2022.109543⟩
Article dans une revue irsn-04122151v3

PERIODIC SAFETY REVIEW IN FRANCE – FOCUS ON NUCLEAR CRITICALITY SAFETY

Matthieu Duluc , Aurelie Bardelay , Regis Cousin , C. Gerin , Igor Le Bars , et al.
11th International conference on Nuclear Criticality Safety, ICNC 2019, Sep 2019, PARIS, France
Communication dans un congrès hal-02894366v1
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FEEDBACK ON JEFF-3.3 AND ENDF/B-VIII.0 NUCLEAR DATA USING A SUITE OF BENCHMARKS FROM THE MORET 5 EXPERIMENTAL VALIDATION DATABASE

Nicolas Leclaire , Frédéric Fernex , Luiz Leal
11th International conference on Nuclear Criticality Safety, ICNC 2019, Sep 2019, PARIS, France. 2019
Poster de conférence hal-02894368v1

Testing thermal scattering law for light water at 600 k using vesta 2.2.0 depletion calculations

Ichou Raphaëlle , Vaibhav Jaiswal , Luiz Leal , Florent Réal , Valérie Vallet
11th International conference on Nuclear Criticality Safety, ICNC 2019, Sep 2019, PARIS, France
Communication dans un congrès hal-02463773v1
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CRISTAL v2: new package for criticality calculations

Jm. Gomit , I. Duhamel , Y. Richet , A. Entringer , C. Magnaud , et al.
Nuclear Criticality Safety Division Topical Meeting (NCSD 2017), Sep 2017, Carlsbad, United States
Communication dans un congrès hal-02417819v1
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Improving the variance in Monte Carlo criticality calculations with adaptative multilevel splitting

Kévin Fröhlicher , Eric Dumonteil , Loic Thulliez , Julien Taforeau , Mariya Brovchenko
PHYSOR 2022 - International Conference on the Physics of Reactors, American Nuclear Society (ANS), May 2022, Pittsburgh, United States
Communication dans un congrès irsn-03948886v1
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Comment converger un calcul Monte-Carlo critique ?

Paul Rovel , Fausto Malvagi
2023
Pré-publication, Document de travail hal-04160720v1
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Patchy nuclear chain reactions

Eric Dumonteil , Rian Bahran , Teresa Cutler , Benjamin Dechenaux , Travis Grove , et al.
Communications Physics, 2021, 4 (1), pp.151. ⟨10.1038/s42005-021-00654-9⟩
Article dans une revue hal-03371772v1

A new PoweR histOry generaTor tOol (PROTO) for French nuclear power stations at IRSN

Miguel Macias Martinez , Benjamin Dechenaux , Jean Baptiste Clavel
Technical Workshop on Fuel Cycle Simulation TWoFCS, Jun 2021, AIX-EN-PROVENCE, France
Communication dans un congrès hal-03513508v1