Analysis of Unprotected Loss of Flow Accident in a Sodium Cooled Fast Reactor Using Coupled Thermal Hydraulics Neutronics Code Astra

Autor:	Yadu Narendran, K. Natesan, K. Devan, A. John Arul
Rok vydání:	2023
DOI:	10.2139/ssrn.4387250
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::c69c67c573a99994322f690a992cbcd4 https://doi.org/10.2139/ssrn.4387250 Zobrazit plný text záznamu