Evaluation of tritium production rate in a gas-cooled reactor with continuous tritium recovery system for fusion reactors

Hideaki Matsuura, Hiroyuki Nakaya, Yasuyuki Nakao, Satoshi Shimakawa, Minoru Goto, Shigeaki Nakagawa, Masabumi Nishikawa

研究成果: Contribution to journalArticle査読

6 被引用数 (Scopus)

抄録

The performance of a high-temperature gas-cooled reactor as a tritium production with continuous tritium recovery system is examined. A gas turbine high-temperature reactor of 300-MWe (600 MW) nominal capacity (GTHTR300) is assumed as the calculation target, and using the continuous-energy Monte Carlo transport code MVP-BURN, burn-up simulations for the three-dimensional entire-core region of the GTHTR300 were performed. A Li loading pattern for the continuous tritium recovery system in the gas-cooled reactor is presented. It is shown that module gas-cooled reactors with a total thermal output power of 3 GW in all can produce ∼6 kg of tritium maximum in a year.

本文言語英語
ページ(範囲)2219-2222
ページ数4
ジャーナルFusion Engineering and Design
88
9-10
DOI
出版ステータス出版済み - 10 1 2013

All Science Journal Classification (ASJC) codes

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering

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