Evaluation of hot spot factors for thermal and hydraulic design of HTTR

So Maruyama, Kiyonobu Yamashita, Nozomu Fujimoto, Isao Murata, Yukio Sudo, Tomoyuki Murakami, Sadao Fujii

研究成果: Contribution to journalArticle査読

10 被引用数 (Scopus)

抄録

High Temperature Engineering Test Reactor (HTTR) is a graphite-moderated and helium gas-cooled reactor with 30 MW in thermal power and 950°C in reactor outlet coolant temperature. One of the major items in thermal and hydraulic design of the HTTR is to evaluate the maximum fuel temperature with a sufficient margin from a viewpoint of integrity of coated fuel particles. Hot spot factors are considered in the thermal and hydraulic design to evaluate the fuel temperature not only under the normal operation condition but also under any transient condition conservatively. This report summarizes the items of hot spot factors selected in the thermal and hydraulic design and their estimated values, and also presents evaluation results of the thermal and hydraulic characteristics of the HTTR briefly.

本文言語英語
ページ(範囲)1186-1194
ページ数9
ジャーナルjournal of nuclear science and technology
30
11
DOI
出版ステータス出版済み - 1 1 1993
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

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