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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
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PyDrag, A User-Friendly Approach to Dragon Deterministic CodeBEPU2024 - Best Estimate Plus Uncertainty International Conference, May 2024, Lucca, Italy
Communication dans un congrès
irsn-04547508v2
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Challenge of PWR new core design simulation A focus on uncertainties due to nuclear data and reflector modellingProgress in Nuclear Energy, 2015, 84, pp.89-96. ⟨10.1016/j.pnucene.2015.01.006⟩
Article dans une revue
hal-02572543v1
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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
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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
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Modeling of heavy reflectors using DONJON-5Annals of Nuclear Energy, 2019, 127, pp.319-325. ⟨10.1016/j.anucene.2018.12.017⟩
Article dans une revue
hal-02524203v1
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Analysis of a VVER-1000 in-core fuel management benchmark with DRAGON and DONJONInternational Journal of Nuclear Energy Science and Technology, 2017, 11, pp.345--376. ⟨10.1504/IJNEST.2017.090658⟩
Article dans une revue
hal-02940141v1
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