Filtrer vos résultats
- 46
- 9
- 5
- 34
- 21
- 3
- 1
- 1
- 46
- 16
- 2
- 11
- 11
- 11
- 8
- 17
- 2
- 57
- 3
- 1
- 1
- 1
- 60
- 8
- 4
- 4
- 3
- 2
- 2
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 15
- 11
- 10
- 8
- 8
- 7
- 7
- 5
- 4
- 4
- 4
- 4
- 4
- 4
- 3
- 3
- 3
- 3
- 3
- 3
- 3
- 3
- 2
- 2
- 2
- 2
- 2
- 2
- 2
- 2
- 2
- 2
- 2
- 2
- 2
- 2
- 2
- 2
- 2
- 2
- 2
- 2
- 2
- 2
- 2
- 2
- 2
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
|
|
triés par
|
Impact of fission spectrum modeling on aging estimations of Pressurized Water Reactor vessels2021 ANS Winter Meeting and Technology Expo, American Nuclear Society, Nov 2021, Washington, United States
Communication dans un congrès
hal-03525466v1
|
|||
|
Development of a multi-zone fuel loading model for scenario studies involving ASTRID-like SFRs with the CLASS code4th 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 CodeInternational Conference on Physics of Reactors 2022 (PHYSOR 2022), American Nuclear Society, May 2022, Pittsburgh, United States
Communication dans un congrès
hal-04122140v1
|
|||
|
Contribution to the validation of the MORET 5 code using the CROCUS reactor physics benchmarkAnnals of Nuclear Energy, 2021, 155, pp.1-12. ⟨10.1016/j.anucene.2021.108164⟩
Article dans une revue
hal-03202427v1
|
||
|
Application of the SPH equivalence technique to the CABRI full core in non-fundamental modePHYSOR 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
|
||
|
Nuclear Data Uncertainties and Adjustments Using Deterministic and Monte-Carlo Methods along with PWR MeasurementsM&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
|
||
|
Neutronic Analysis of the European Sodium Fast Reactor: Part I—Fresh Core ResultsJournal of Nuclear Engineering and Radiation Science, 2021, 8 (1), pp.11301. ⟨10.1115/1.4048905⟩
Article dans une revue
irsn-04122162v3
|
||
|
Generational Variance Reduction in Monte Carlo Criticality Simulations as a Way of Mitigating Unwanted CorrelationsNuclear Science and Engineering, 2023, pp.1-18. ⟨10.1080/00295639.2023.2193089⟩
Article dans une revue
irsn-04122114v1
|
||
|
A Detailed Analysis of the H.B. Robinson-2 Reactor Pressure Vessel Dosimetry BenchmarkEnergies, 2022, 15 (14), pp.5098. ⟨10.3390/en15145098⟩
Article dans une revue
irsn-04122073v1
|
||
|
Design Methodology for Fuel Debris Experiment in the New STACY FacilityICNC 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
|
||
|
Neutron spectrum unfolding using two architectures of convolutional neural networksNuclear Engineering and Technology, 2023, 55 (6), pp.2276 - 2282. ⟨10.1016/j.net.2023.03.025⟩
Article dans une revue
hal-04104489v1
|
||
|
On the validation of VESTA 2.2.0 using the ARIANE-GU3 samplePHYSOR 2020, PHYSOR, Mar 2020, CAMBRIDGE, United Kingdom. pp.10005, ⟨10.1051/epjconf/202124710005⟩
Communication dans un congrès
hal-03523803v1
|
||
|
On the use of graph theory to interpret the output results from a Monte-Carlo depletion codeJournal of Nuclear Engineering and Radiation Science, 2021, 195 (5), pp.538-554. ⟨10.1080/00295639.2020.1847980⟩
Article dans une revue
hal-03191108v1
|
||
|
Global and flexible models for Sodium-cooled Fast Reactors in fuel cycle simulationsAnnals of Nuclear Energy, 2019, 128, pp.69-76. ⟨10.1016/j.anucene.2018.12.037⟩
Article dans une revue
hal-01975524v1
|
||
|
Neutronic Analysis of the European Sodium Fast Reactor: Part II - Burnup ResultsJournal of Nuclear Engineering and Radiation Science, 2021, 8 (1), pp.11302. ⟨10.1115/1.4048765⟩
Article dans une revue
irsn-04122521v1
|
||
|
Percolation properties of the neutron population in nuclear reactorsPhysical 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 validation15th International Conference on Nuclear Data for Science and Technology (ND2022), Jul 2022, Scramento (virtual evant), United States
Communication dans un congrès
hal-03759208v1
|
|||
|
A Versatile Methodology for Reactor Pressure Vessel Aging AssessmentsNuclear Science and Engineering, 2022, 196 (4), pp.455-477. ⟨10.1080/00295639.2021.1991761⟩
Article dans une revue
hal-03636003v1
|
||
|
Investigating fission distribution behavior under various homogenization techniques for asymmetrical fuel assemblies and different reflector equivalence methodsAnnals of Nuclear Energy, 2021, 157, ⟨10.1016/j.anucene.2021.108221⟩
Article dans une revue
hal-03207089v1
|
||
|
PyNjoy2016: an Open Source System for Producing Cross Sections Libraries for DRAGON5 and SERPENT2M&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
|
||
|
Impact du déploiement de réacteurs de type ASTRID sur la gestion dynamique du plutonium dans des scénarios de transitions électronucléairesPhysique Nucléaire Théorique [nucl-th]. Université Paris Saclay (COmUE), 2019. Français. ⟨NNT : 2019SACLS494⟩
Thèse
tel-02628512v1
|
||
|
Functional Expansion Tallies using Fission Matrix Eigenmodes for Full Core Criticality SimulationsAnnals 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 SAFETY11th International conference on Nuclear Criticality Safety, ICNC 2019, Sep 2019, PARIS, France
Communication dans un congrès
hal-02894366v1
|
|||
|
FEEDBACK ON JEFF-3.3 AND ENDF/B-VIII.0 NUCLEAR DATA USING A SUITE OF BENCHMARKS FROM THE MORET 5 EXPERIMENTAL VALIDATION DATABASE11th 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 calculations11th International conference on Nuclear Criticality Safety, ICNC 2019, Sep 2019, PARIS, France
Communication dans un congrès
hal-02463773v1
|
|||
|
CRISTAL v2: new package for criticality calculationsNuclear Criticality Safety Division Topical Meeting (NCSD 2017), Sep 2017, Carlsbad, United States
Communication dans un congrès
hal-02417819v1
|
||
|
Improving the variance in Monte Carlo criticality calculations with adaptative multilevel splittingPHYSOR 2022 - International Conference on the Physics of Reactors, American Nuclear Society (ANS), May 2022, Pittsburgh, United States
Communication dans un congrès
irsn-03948886v1
|
||
|
Comment converger un calcul Monte-Carlo critique ?2023
Pré-publication, Document de travail
hal-04160720v1
|
||
|
Patchy nuclear chain reactionsCommunications 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 IRSNTechnical Workshop on Fuel Cycle Simulation TWoFCS, Jun 2021, AIX-EN-PROVENCE, France
Communication dans un congrès
hal-03513508v1
|
- 1
- 2