Core configuration of a gas-cooled reactor as a tritium production device for fusion reactor

H. Nakaya, Hideaki Matsuura, Y. Nakao, S. Shimakawa, M. Goto, S. Nakagawa, M. Nishikawa

Research output: Contribution to journalArticle

13 Citations (Scopus)

Abstract

The performance of a high-temperature gas-cooled reactor as a tritium production device is examined, assuming the compound LiAlO2 as the tritium-producing material. A gas turbine high-temperature reactor of 300 MWe nominal capacity (GTHTR300) is assumed as the calculation target, and using the continuous-energy Monte Carlo transport code MVP-BURN, burn-up simulations are carried out. To load sufficient Li into the core, LiAlO2 is loaded into the removable reflectors that surround the ring-shaped fuel blocks in addition to the burnable poison insertion holes. It is shown that module high-temperature gas-cooled reactors with a total thermal output power of 3 GW can produce almost 8 kg of tritium in a year.

Original languageEnglish
Pages (from-to)505-509
Number of pages5
JournalNuclear Engineering and Design
Volume271
DOIs
Publication statusPublished - Jan 1 2014

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Safety, Risk, Reliability and Quality
  • Waste Management and Disposal
  • Mechanical Engineering

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