Nuclear and thermal feasibility of lithium-loaded high temperature gas-cooled reactor for tritium production for fusion reactors

Minoru Goto, Keisuke Okumura, Shigeaki Nakagawa, Yoshitomo Inaba, Hideaki Matsuura, Hiroyuki Nakaya, Kazunari Katayama

研究成果: Contribution to journalArticle査読

1 被引用数 (Scopus)

抄録

A high-temperature, gas-cooled reactor (HTGR) is proposed as a tritium production device that has the potential to produce a large amount of tritium using the 6Li(n,α)T reaction without major changes to the original reactor core design. In an HTGR design, generally, boron is loaded into the core as a burnable poison to suppress excess reactivity. In this study, lithium is loaded into the HTGR core aiming to produce thermal energy and tritium simultaneously and is loaded instead of boron as a burnable poison. The nuclear characteristics and fuel temperature were analyzed to confirm the nuclear and thermal feasibility of a lithium-loaded HTGR. It was shown that the analysis results satisfied the design requirements and hence the nuclear and thermal feasibility was confirmed for a lithium-loaded HTGR that produces thermal energy and tritium.

本文言語英語
ページ(範囲)357-361
ページ数5
ジャーナルFusion Engineering and Design
136
DOI
出版ステータス出版済み - 11 2018

All Science Journal Classification (ASJC) codes

  • 土木構造工学
  • 原子力エネルギーおよび原子力工学
  • 材料科学(全般)
  • 機械工学

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