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

T. Norimatsu, H. Saika, H. Homma, M. Nakai, Satoshi 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 - Jan 1 2011

Fingerprint

Laser fusion
laser fusion
Tritium
fusion reactors
Fusion reactors
tritium
Conceptual design
leakage
heat exchangers
Heat exchangers
heat
cycles
oxidizers
liquid metals
Liquid metals
Water
water
tubes
Noble Gases
coolants

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

Leakage control of tritium through heat cycles of conceptual-design, laser-fusion reactor koyo-F. / Norimatsu, T.; Saika, H.; Homma, H.; Nakai, M.; Fukada, Satoshi; Sagara, A.; Azechi, H.

In: Fusion Science and Technology, Vol. 60, No. 3, 01.01.2011, p. 893-896.

Research output: Contribution to journalArticle

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, vol. 60, no. 3, pp. 893-896. https://doi.org/10.13182/FST11-A12561
Norimatsu, T. ; Saika, H. ; Homma, H. ; Nakai, M. ; Fukada, Satoshi ; Sagara, A. ; Azechi, H. / Leakage control of tritium through heat cycles of conceptual-design, laser-fusion reactor koyo-F. In: Fusion Science and Technology. 2011 ; Vol. 60, No. 3. pp. 893-896.
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