検索対象:     
報告書番号:
※ 半角英数字
 年 ~ 
 年

Plasma heating test on fuel assembly degradation

模擬燃料集合体破損試験

山下 拓哉  ; 佐藤 一憲 

Yamashita, Takuya; Sato, Ikken

A large uncertainty is present in understanding of BWR accident progression behavior. A series of tests were conducted to provide experimental data that address uncertainties. As a result, useful information on core state just before slumping was obtained. This information will help us to comprehend core degradation in BWRs like those in the Fukushima Dai-ichi Nuclear Power Plant (1F).

Access

:

- Accesses

InCites™

:

Altmetrics

:

[CLARIVATE ANALYTICS], [WEB OF SCIENCE], [HIGHLY CITED PAPER & CUP LOGO] and [HOT PAPER & FIRE LOGO] are trademarks of Clarivate Analytics, and/or its affiliated company or companies, and used herein by permission and/or license.