Leakage control of tritium through heat cycles of conceptual-design, laser-fusion reactor koyo-F

T. Norimatsu, H. Saika, H. Homma, M. Nakai, S. Fukada, A. Sagara, H. Azechi

Research output: Contribution to journalArticle

4 Citations (Scopus)

Abstract

To reduce the tritium permeation from the primary liquid metal loop to the secondary water loop, a heat exchanger concept that incorporates small diameter tubes containing an oxidizer was proposed. An inert gas containing a small amount of oxidizer flows in the small tubes oxiding tritium that comes from the primary liquid metal coolant. The tritiated water is sent to a tritium recovery system minimizing leakage to the secondary water loop. Our evaluation results indicated that the tritium leakage through the heat exchanger was reduced to 1/105 with an acceptable increase in the size of the heat exchanger.

Original languageEnglish
Pages (from-to)893-896
Number of pages4
JournalFusion Science and Technology
Volume60
Issue number3
DOIs
Publication statusPublished - Oct 2011

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All Science Journal Classification (ASJC) codes

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

Cite this

Norimatsu, T., Saika, H., Homma, H., Nakai, M., Fukada, S., Sagara, A., & Azechi, H. (2011). Leakage control of tritium through heat cycles of conceptual-design, laser-fusion reactor koyo-F. Fusion Science and Technology, 60(3), 893-896. https://doi.org/10.13182/FST11-A12561