SIMMER-III applications to fuel-coolant interactions

K. Morita, Sa Kondo, Y. Tobita, D. J. Brear

研究成果: Contribution to journalArticle査読

37 被引用数 (Scopus)

抄録

The main purpose of the fast reactor safety analysis code, SIMMER-III, is to provide a numerical simulation of complex multiphase, multicomponent flow problems essential to investigate core disruptive accidents in liquid-metal fast reactors (LMFRs). However, the code is designed to be sufficiently flexible to be applied to a variety of multiphase flows, in addition to LMFR safety issues. In the present study, some typical experiments relating to fuel-coolant interactions (FCIs) have been analyzed by SIMMER-III to demonstrate that the code is applicable to such complex and highly transient multiphase flow situations. It is shown that SIMMER-III can reproduce the premixing phase both in water and sodium systems as well as the propagation of steam explosion. It is thus demonstrated the code is basically capable of simulating integral multiphase thermal-hydraulic problems included in FCI experiments.

本文言語英語
ページ(範囲)337-357
ページ数21
ジャーナルNuclear Engineering and Design
189
1
DOI
出版ステータス出版済み - 5 11 1999
外部発表はい

All Science Journal Classification (ASJC) codes

  • 核物理学および高エネルギー物理学
  • 原子力エネルギーおよび原子力工学
  • 材料科学(全般)
  • 安全性、リスク、信頼性、品質管理
  • 廃棄物管理と処理
  • 機械工学

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