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A feasibility study of a High Temperature Gas-cooled Reactor (HTGR) for tritium production using $^{6}$ Li(n,)T reaction for fusion reactors has been conducted. In this study, the burn-up chain was modified to treat $^{6}$ Li(n,a)T reaction directory in neutronics calculations, and then the feasibility study was performed from the view point of nuclear characteristics using SRAC code system, which has experience in neutronics analysis of HTGRs.

Oral presentation

Evaluation of nuclear and thermal characteristics of lithium loaded HTGR for tritium production

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

no journal, ,

A feasibility study of a High Temperature Gas-cooled Reactor (HTGR) for tritium production using $^{6}$ Li(n,)T reaction for fusion reactors has been conducted. In this study, the burn-up chain was modified to treat $^{6}$ Li(n,)T reaction directory in neutronics calculations, and then the feasibility study was performed from the view point of nuclear and thermal characteristics using SRAC code system, which has experience in neutronics analysis of HTGRs.

Oral presentation

Study on T production using high-temperature gas-cooled reactor for fusion reactors, 4; Feasibility study on irradiation test for tritium production capsule

Ishitsuka, Etsuo; Ho, H. Q.; Shimazaki, Yosuke; Nakagawa, Shigeaki; Goto, Minoru; Matsuura, Hideaki*; Otsuka, Teppei*; Katayama, Kazunari*; Iigaki, Kazuhiko

no journal, ,

As part of the development of tritium production using a high-temperature gas-cooled reactor for the initial loading of a fusion reactor, an irradiation test of a tritium production capsule has been studied. In this presentation, a feasibility study on irradiation test using JRR-3 will be introduced.

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Study on defect state and tritium behavior in neutron-irradiated Li-Al alloy

Procurement of tritium for fusion reactor; A design study of facility for production of fusion fuel tritium

Tritium production technology

Test production of tritium 3.7TBq level from neutron-irradiated $^{6}$ LiAl alloy targets

Production of fusion reactor fuel tritium and its chemistry

Lithium-production and breeding of tritium for nuclear fusion reactors

Evaluation of nuclear characteristics of lithium loaded HTGR for tritium production for fusion reactors

Evaluation of nuclear and thermal characteristics of lithium loaded HTGR for tritium production

Study on T production using high-temperature gas-cooled reactor for fusion reactors, 4; Feasibility study on irradiation test for tritium production capsule