Post-facta analysis of the TMI accident (I): analysis of thermal hydraulic behavior by use of RELAP4/MOD6/U4/J2

F. Tanabe*, K. Yoshida, K. Matsumoto, T. Shimooke

*この研究の対応する著者

研究成果: Article査読

5 被引用数 (Scopus)

抄録

A thorough analysis of the thermal-hydraulic behavior of the TMI-2 reactor during the first three hours of the accident on March 28, 1979 was carried out by use of RELAP4/MOD6/U4/J2 computer program. The analysis includes the loss of feedwater transient, the small break loss-of-coolant accident (LOCA) through the pressurizer pilot-operated relief valve (PORV) and the distribution of hydrogen generated by the zirconium-water reaction. It took account of the effects of the pressurizer heaters and of the presence of the hydrogen. The calculated result shows good agreement with the accident record, and the effects of some key parameters have become better understood. This analysis shows that the tops of active fuel rods would have begun to be exposed at 6490 s into the accident and the core mixture level remained at a height of 3.4 to 4 ft from the bottom of the core for about 40 min.

本文言語English
ページ(範囲)3-35
ページ数33
ジャーナルNuclear Engineering and Design
69
1
DOI
出版ステータスPublished - 1982 4 2
外部発表はい

ASJC Scopus subject areas

  • エネルギー工学および電力技術
  • 原子力エネルギーおよび原子力工学
  • 土木構造工学
  • 機械工学
  • 安全性、リスク、信頼性、品質管理

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