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

Research output: Contribution to journalArticle

9 Citations (Scopus)

Abstract

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.

Original languageEnglish
Pages (from-to)1186-1194
Number of pages9
Journaljournal of nuclear science and technology
Volume30
Issue number11
DOIs
Publication statusPublished - Jan 1 1993
Externally publishedYes

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

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