Validation of analysis models on relocation behavior of molten core materials in sodium-cooled fast reactors based on the melt discharge experiment

In order to improve the safety of nuclear power plants, it is necessary to make sure measures against their severe accidents. Especially, in the case of a sodium-cooled fast reactor, there is a possibility that molten core material would be discharged through control rod guide tubes into the inlet c...

Descripción completa

Guardado en:
Detalles Bibliográficos
Autores principales: Kai IGARASHI, Takaaki SAKAI, Shinya KATO, Ken-ichi MATSUBA, Kenji KAMIYAMA
Formato: article
Lenguaje:EN
Publicado: The Japan Society of Mechanical Engineers 2021
Materias:
Acceso en línea:https://doaj.org/article/2b733b23142447b898c29f235e84eb23
Etiquetas: Agregar Etiqueta
Sin Etiquetas, Sea el primero en etiquetar este registro!