Research on core melt accident analysis of LWRs

Abe, Kiyoharu

Tokyo Daigaku Gakui Rombun, 0, 245 Pages, 1994/09

http://hdl.handle.net/2261/50915

no abstracts in English

Sensitivity study on PWR source terms with THALES/ART code package and effects of in-vessel thermal-hydraulic models

Abe, Kiyoharu; Watanabe, Norio; Ida, Mitsuo; Sakamoto, Toru; Ishigami, Tsutomu; Harami, Taikan

Proc.on Probabilistic Safety Assessment and Risk Management PSA87, Vol.3, p.945 - 950, 1987/00

no abstracts in English

Development of computer code system THALES for thermal-hydrauice analysis of core meltdown accident, I; Outlines of code system and analytical models in each code

; *; Watanabe, Norio; *

Nihon Genshiryoku Gakkai-Shi, 27(11), p.1035 - 1046, 1985/00

https://doi.org/10.3327/jaesj.27.1035

no abstracts in English

Description of THALES-CV1: A Computer Code for Evaluating Containment Temperature and Pressure During Core Meltdown Accident

; ; Watanabe, Norio; *; *; *

JAERI-M 83-037, 96 Pages, 1983/03

JAERI-M-83-037.pdf:3.12MB

no abstracts in English

Design features and safety assessment of a sodium-cooled fast reactor in Japan for mitigation of severe accidents

Yamano, Hidemasa

no journal, , 

Four phases are categorized in the core degradation process: Initiating, transition, material relocation and cooling phase. In this report, specific design features for each phase are shown as well as the safety assessment results to demonstrate their effectiveness.