Study of Tritium Production for Fusion Reactors Using High-Temperature Gas-Cooled Reactors

H. MatsuuraApplied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Motooka, Fukuoka 819-0395, Japan

T. YasumotoApplied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Motooka, Fukuoka 819-0395, Japan

S. KouchiApplied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Motooka, Fukuoka 819-0395, Japan

H. NakayaApplied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Motooka, Fukuoka 819-0395, Japan

S. ShimakawaJapan Atomic Energy Agency, 4002 Oarai, Ibaraki 319-1393, Japan

Y. NakaoApplied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Motooka, Fukuoka 819-0395, Japan

M. GotoJapan Atomic Energy Agency, 4002 Oarai, Ibaraki 319-1393, Japan

S. NakagawaJapan Atomic Energy Agency, 4002 Oarai, Ibaraki 319-1393, Japan

M. NishikawaGraduate School of Engineering Science, Kyushu University, 6-10-1 Hakozaki, Fukuoka 812-8581, Japan

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Abstract

The performance of a high-temperature gas-cooled reactor as a tritium production device was examined. A gas turbine high-temperature reactor of 300 MWe nominal capacity (GTHTR300) was assumed as the calculation target of a typical gas-cooled reactor, and using the continuous-energy Monte Carlo transport code MVP-BURN, burn-up simulations for the entire-core region of GTHTR300 were carried out considering its unique double heterogeneity structure. It was shown that gas-cooled reactors with thermal output power of 3 GW in all can produce 6~10 kg of tritium in a year.

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Study of Tritium Production for Fusion Reactors Using High-Temperature Gas-Cooled Reactors

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Study of Tritium Production for Fusion Reactors Using High-Temperature Gas-Cooled Reactors

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