Filtrer vos résultats
- 38
- 7
- 6
- 26
- 16
- 7
- 2
- 46
- 8
- 3
- 1
- 1
- 1
- 1
- 1
- 2
- 2
- 9
- 7
- 7
- 7
- 7
- 6
- 46
- 5
- 4
- 2
- 1
- 1
- 1
- 1
- 47
- 8
- 5
- 4
- 4
- 4
- 4
- 4
- 2
- 2
- 2
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 12
- 8
- 7
- 6
- 5
- 5
- 5
- 4
- 4
- 4
- 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
- 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
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
- 1
51 résultats
|
|
|
triés par
|
Importance of the axial burn-up modelling for fuel assembly nozzles activation calculationInternational Conference on the Physics of Reactors, PHYSOR, May 2022, PITTSBURGH (Virtual), United States
Communication dans un congrès
hal-03746147v1
|
|||
|
|
Improving variance estimation for time-dependent detectors in Monte Carlo dynamic calculations using adaptive sampling of neutronsM&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-04122131v1
|
||
|
|
Neutronic, thermohydraulic and thermomechanical coupling for the modeling of criticality accidents in nuclear systemsGénie civil nucléaire. Université Grenoble Alpes [2020-..], 2020. English. ⟨NNT : 2020GRALI078⟩
Thèse
tel-03172978v1
|
||
|
|
Neutronic modeling strategies for a liquid fuel transient calculationInternational Conference on Physics of Reactors 2020: Transition to a Scalable Nuclear Future, Mar 2020, Cambridge, United Kingdom. pp.06013, ⟨10.1051/epjconf/202124706013⟩
Communication dans un congrès
hal-03325385v1
|
||
|
|
Design of TEX-MOX critical experiments varying neutron spectrumICNC 2023 - The 12th International Conference on Nuclear Criticality Safety, JAEA, Oct 2023, Sendai, Japan
Communication dans un congrès
hal-04627968v1
|
||
|
|
PIN POWER CALCULATION SCHEME FOR REACTOR PRESSURE VESSEL FAST NEUTRON FLUENCE ESTIMATIONPHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, Mar 2020, Cambridge, France. pp.02029, ⟨10.1051/epjconf/202124702029⟩
Communication dans un congrès
irsn-04666996v1
|
||
|
|
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
|
||
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
|
|||
|
|
Etudes de la convergence d'un calcul Monte Carlo de criticité : utilisation d'un calcul déterministe et détection automatisée du transitoirePhysique Nucléaire Expérimentale [nucl-ex]. Université de Grenoble, 2012. Français. ⟨NNT : 2012GRENY063⟩
Thèse
tel-00846504v1
|
||
|
|
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
|
||
|
|
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
|
||
|
|
Evaluation of thermal scattering law for light water based on new time-of-flight measurements at the Institute Laue-Langevin (ILL)PHYTRA4 - The 4th International Conference on Physics and Technology of Reactors and Applications, Sep 2018, Marrakech, Morocco
Communication dans un congrès
hal-02377307v1
|
||
|
|
On the use of different variance reduction techniques within MCNP to calculate the flux on the concrete walls of a pressurized water reactorInternational Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2019), American Nuclear Society (ANS), Aug 2019, Portland (OR), United States. pp.Pages 104-119
Communication dans un congrès
hal-04513231v1
|
||
Resonance Parameters and Covariance Evaluations for the Gadolinium Isotopes11th International conference on Nuclear Criticality Safety, ICNC 2019, Sep 2019, PARIS, France
Communication dans un congrès
hal-02478476v1
|
|||
Isotope studies of the Caspian Sea: Climatic record from the bottom sediments (preliminary results)Internat. Atomic Energy Agency, 1997, pp.1-19
Article dans une revue
hal-04478917v1
|
|||
|
|
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 technologyInternational Conference on Physics of Reactors 2020: Transition to a Scalable Nuclear Future, Mar 2020, Cambridge, United Kingdom. pp.02040, ⟨10.1051/epjconf/202124702040⟩
Communication dans un congrès
hal-03325387v1
|
||
|
|
Development of a multi-zone irradiation model for scenario studies involving ASTRID-like SFRsICAPP 2019 – International Congress on Advances in Nuclear Power Plants, May 2019, Juan-les-pins, France
Communication dans un congrès
hal-04125760v1
|
||
|
|
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
|
||
Development Progress of the GAIA nuclear data processing softwareNuclear Data Sheets, 2014, 118 (1), pp.491-493. ⟨10.1016/j.nds.2014.04.115⟩
Article dans une revue
hal-02611868v1
|
|||
|
|
Measurement of double differential cross-section of light water at high temperature and pressure to generate S(α,β)EPJ Web of Conferences, 2017, 146, pp.13006. ⟨10.1051/epjconf/201714613006⟩
Article dans une revue
hal-01618681v1
|
||
|
|
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
|
||
|
|
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
|
||
|
|
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
|
||
|
|
REGAL International Program: Analysis of experimental data for depletion code validationAnnals of Nuclear Energy, 2022, 172, pp.109057. ⟨10.1016/j.anucene.2022.109057⟩
Article dans une revue
irsn-04588935v1
|
||
|
|
PyDrag, A User-Friendly Approach to Dragon Deterministic CodeBEPU2024 - Best Estimate Plus Uncertainty International Conference, N.IN.E. (Nuclear and Industrial Engineering), May 2024, Lucca, Italy
Communication dans un congrès
irsn-04547508v2
|
||
|
|
Analysis of transition scenario from a PWR to a SFR fleet simulated with the class code14th International Nuclear Fuel Cycle Conference GLOBAL 2019, and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019, Sep 2019, Seattle, United States. pp.202-211
Communication dans un congrès
hal-04122132v2
|
||
|
|
Criticality safety of fuel assemblies with missing fuel rodsAnnals of Nuclear Energy, 2024, 198, pp.110273. ⟨10.1016/j.anucene.2023.110273⟩
Article dans une revue
irsn-04346500v1
|
||
|
|
Estimation de l'incertitude due à la méconnaissance des données nucléaires sur la puissance résiduelle d'un combustible irradiéPhysique Numérique [physics.comp-ph]. 2024
Mémoire d'étudiant
irsn-04682059v1
|
||
|
|
An Analysis of a Coarse-Group Subgroup Method Based on the Physical Probability Tables in APOLLO3®Nuclear Science and Engineering, 2024, Select papers from the M&C 2023 special issue, pp.1-14. ⟨10.1080/00295639.2024.2340143⟩
Article dans une revue
irsn-04662885v2
|
||
|
|
Capteurs à fibres optiques répartis pour la surveillance du corium en cas d'accident grave de réacteur nucléaire avec percement de la cuve : le projet ANR RSNR DISCOMSJNOG 2019 - 39e Journées Nationales d’Optique Guidée, Université Paris-Saclay, Jul 2019, Saclay, France
Communication dans un congrès
cea-04094221v1
|
- 1
- 2