CFD study of the PTS experiment in ROCOM test facility
With the aging of nuclear reactors, embrittlement of the reactor pressure vessel (RPV) steel, as a consequence of routine operations, is highly probable. To ensure operational integrity and safety, prediction and mitigation of compromising damage, brought on by pressurized thermal shock (PTS) follow...
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| Principais autores: | , , , |
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| Formato: | Artigo |
| Idioma: | Inglês |
| Publicado em: |
Elsevier
2020-12-01
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| coleção: | Nuclear Engineering and Technology |
| Assuntos: | |
| Acesso em linha: | http://www.sciencedirect.com/science/article/pii/S1738573320300322 |
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