Study of tritium production for fusion reactors using high-Temperature gas-Cooled reactors

H. Matsuura; T. Yasumoto; S. Kouchi; H. Nakaya; S. Shimakawa; Y. Nakao; M. Goto; S. Nakagawa; M. Nishikawa

doi:10.13182/FST12-A13431

Study of tritium production for fusion reactors using high-Temperature gas-Cooled reactors

H. Matsuura, T. Yasumoto, S. Kouchi, H. Nakaya, S. Shimakawa, Y. Nakao, M. Goto, S. Nakagawa, M. Nishikawa

Nuclear Energy Systems

Research output: Contribution to journal › Article › peer-review

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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.

Original language	English
Pages (from-to)	268-272
Number of pages	5
Journal	Fusion Science and Technology
Volume	61
Issue number	1 T
DOIs	https://doi.org/10.13182/FST12-A13431
Publication status	Published - Jan 2012

All Science Journal Classification (ASJC) codes

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

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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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AU - Matsuura, H.

AU - Yasumoto, T.

AU - Kouchi, S.

AU - Nakaya, H.

AU - Shimakawa, S.

AU - Nakao, Y.

AU - Goto, M.

AU - Nakagawa, S.

AU - Nishikawa, M.

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N2 - 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.

AB - 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

Abstract

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