Post-facta analysis of the TMI accident (II): Analysis of fuel rod behavior and core damage estimation by use of TOODEE2-J

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

研究成果: Article査読

2 被引用数 (Scopus)

抄録

By use of the TOODEE2-J computer program, an analysis was carried out of the fuel rod behavior, and core damage was estimated for the TMI-2 reactor during the first three hours of the accident on March 28, 1979. The boundary conditions (e.g. core mixture level, steam flow rate and core inlet flow) are based on a thermal-hydraulic analysis by the RELAP4/MOD6/U4/J2 computer program. The calculated results suggest that bursting of almost all rods except peripheral low-powered rods occurred, and that a large part of the zircaloy cladding exceeded the eutectic temperature to form a liquid phase of ZrUO. A total of 43.5% of the zircaloy in the fueled part of the core had been converted to zirconium-dioxide by three hours into the accidient, and major damage to the fuel rods had also occured by then.

本文言語English
ページ(範囲)37-42
ページ数6
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

  • Energy Engineering and Power Technology
  • Nuclear Energy and Engineering
  • Civil and Structural Engineering
  • Mechanical Engineering
  • Safety, Risk, Reliability and Quality

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