Coupled modeling of irradiated fuel thermochemistry and gas diffusion during severe accidents-Reference-Cited by-同舟云学术

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Coupled modeling of irradiated fuel thermochemistry and gas diffusion during severe accidents

Published:2022-03 Issue: Volume:560 Page:153429
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Germain A.,Sercombe J.,Riglet-Martial C.^ORCID,Introïni C.^ORCID,Noirot L.^ORCID,Pontillon Y.,Maugis Ph.^ORCID

Funder

Commissariat à l'Énergie Atomique et aux Énergies Alternatives

Electricité de France

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference43 articles.

1. Overview of experimental programs on core melt progression and fission product release behaviour;Lewis;Journal of Nuclear Materials,2008

2. PHEBUS FP: a severe accident research programme for current and advanced light water reactors;Schwarz;Nuclear Engineering and Design,1999

3. The HEVA experimental program;Leveque;Nuclear Technology,1994

4. Behaviour of fission products under severe PWR accident conditions VERCORS experimental program - Part 1: General description of the programme;Pontillon;Nuclear Engineering and Design,2010

5. Behaviour of fission products under severe PWR accident conditions: The VERCORS experimental program - Part 2: Release and transport of fission gases and volatile fission products;Pontillon;Nuclear Engineering and Design,2010

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1. Integral-scale validation of the SCIANTIX code for Light Water Reactor fuel rods;Journal of Nuclear Materials;2024-12

2. ALCYONE: the fuel performance code of the PLEIADES platform dedicated to PWR fuel rods behavior;Annals of Nuclear Energy;2024-11

3. The SCIANTIX code for fission gas behaviour: Status, upgrades, separate-effect validation, and future developments;Journal of Nuclear Materials;2023-12

4. Oriented intra-granular bubble transport due to coupling of pinned bubble growth and dislocation climb;Journal of Nuclear Materials;2023-04

5. Characterisation of 3000 ppm Cr₂O₃ doped UO₂ and its precipitates;Journal of Raman Spectroscopy;2023-02-24

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