Validation of the nuclear design code system for the HTTR using the criticality assembly VHTRC

Nozomu Fujimoto, Naoki Nojiri, Kiyonobu Yamashita

研究成果: Contribution to journalArticle査読

3 被引用数 (Scopus)

抄録

The high temperature engineering test reactor is the first block-type HTGR designed for a 950 °C outlet gas temperature which uses low-enriched uranium fuel with burnable poison rod. For validation of the nuclear design code system for the HTTR, a critical assembly of VHTRC had been constructed. The calculation uncertainties of effective multiplication factor, neutron flux distribution, burnable poison reactivity worth, and control rod worth, temperature coefficients were evaluated. Calculation accuracy of a Monte Carlo code is also evaluated.

本文言語英語
ページ(範囲)155-162
ページ数8
ジャーナルNuclear Engineering and Design
233
1-3
DOI
出版ステータス出版済み - 10 1 2004
外部発表はい

All Science Journal Classification (ASJC) codes

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

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