Evaluation of tritium production rate in a gas-cooled reactor with continuous tritium recovery system for fusion reactors

Hideaki Matsuura; Hiroyuki Nakaya; Yasuyuki Nakao; Satoshi Shimakawa; Minoru Goto; Shigeaki Nakagawa; Masabumi Nishikawa

doi:10.1016/j.fusengdes.2013.05.022

Evaluation of tritium production rate in a gas-cooled reactor with continuous tritium recovery system for fusion reactors

Hideaki Matsuura, Hiroyuki Nakaya, Yasuyuki Nakao, Satoshi Shimakawa, Minoru Goto, Shigeaki Nakagawa, Masabumi Nishikawa

Nuclear Energy Systems

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

7 Citations (Scopus)

Abstract

The performance of a high-temperature gas-cooled reactor as a tritium production with continuous tritium recovery system is examined. A gas turbine high-temperature reactor of 300-MWe (600 MW) nominal capacity (GTHTR300) is assumed as the calculation target, and using the continuous-energy Monte Carlo transport code MVP-BURN, burn-up simulations for the three-dimensional entire-core region of the GTHTR300 were performed. A Li loading pattern for the continuous tritium recovery system in the gas-cooled reactor is presented. It is shown that module gas-cooled reactors with a total thermal output power of 3 GW in all can produce ∼6 kg of tritium maximum in a year.

Original language	English
Pages (from-to)	2219-2222
Number of pages	4
Journal	Fusion Engineering and Design
Volume	88
Issue number	9-10
DOIs	https://doi.org/10.1016/j.fusengdes.2013.05.022
Publication status	Published - Oct 2013

All Science Journal Classification (ASJC) codes

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

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10.1016/j.fusengdes.2013.05.022

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@article{4127562151544cf885b0a1b7c49a254a,

title = "Evaluation of tritium production rate in a gas-cooled reactor with continuous tritium recovery system for fusion reactors",

abstract = "The performance of a high-temperature gas-cooled reactor as a tritium production with continuous tritium recovery system is examined. A gas turbine high-temperature reactor of 300-MWe (600 MW) nominal capacity (GTHTR300) is assumed as the calculation target, and using the continuous-energy Monte Carlo transport code MVP-BURN, burn-up simulations for the three-dimensional entire-core region of the GTHTR300 were performed. A Li loading pattern for the continuous tritium recovery system in the gas-cooled reactor is presented. It is shown that module gas-cooled reactors with a total thermal output power of 3 GW in all can produce ∼6 kg of tritium maximum in a year.",

author = "Hideaki Matsuura and Hiroyuki Nakaya and Yasuyuki Nakao and Satoshi Shimakawa and Minoru Goto and Shigeaki Nakagawa and Masabumi Nishikawa",

note = "Funding Information: The authors acknowledge many researchers in the Japanese fusion community for fruitful discussions concerning the tritium supply problem in future fusion devices. This research was supported by the Ministry of Education, Science, Sports and Culture, Grant-in-Aid for challenging Exploratory Research, 23656574 and 25630421.",

year = "2013",

month = oct,

doi = "10.1016/j.fusengdes.2013.05.022",

language = "English",

volume = "88",

pages = "2219--2222",

journal = "Fusion Engineering and Design",

issn = "0920-3796",

publisher = "Elsevier BV",

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T1 - Evaluation of tritium production rate in a gas-cooled reactor with continuous tritium recovery system for fusion reactors

AU - Matsuura, Hideaki

AU - Nakaya, Hiroyuki

AU - Nakao, Yasuyuki

AU - Shimakawa, Satoshi

AU - Goto, Minoru

AU - Nakagawa, Shigeaki

AU - Nishikawa, Masabumi

N1 - Funding Information: The authors acknowledge many researchers in the Japanese fusion community for fruitful discussions concerning the tritium supply problem in future fusion devices. This research was supported by the Ministry of Education, Science, Sports and Culture, Grant-in-Aid for challenging Exploratory Research, 23656574 and 25630421.

PY - 2013/10

Y1 - 2013/10

N2 - The performance of a high-temperature gas-cooled reactor as a tritium production with continuous tritium recovery system is examined. A gas turbine high-temperature reactor of 300-MWe (600 MW) nominal capacity (GTHTR300) is assumed as the calculation target, and using the continuous-energy Monte Carlo transport code MVP-BURN, burn-up simulations for the three-dimensional entire-core region of the GTHTR300 were performed. A Li loading pattern for the continuous tritium recovery system in the gas-cooled reactor is presented. It is shown that module gas-cooled reactors with a total thermal output power of 3 GW in all can produce ∼6 kg of tritium maximum in a year.

AB - The performance of a high-temperature gas-cooled reactor as a tritium production with continuous tritium recovery system is examined. A gas turbine high-temperature reactor of 300-MWe (600 MW) nominal capacity (GTHTR300) is assumed as the calculation target, and using the continuous-energy Monte Carlo transport code MVP-BURN, burn-up simulations for the three-dimensional entire-core region of the GTHTR300 were performed. A Li loading pattern for the continuous tritium recovery system in the gas-cooled reactor is presented. It is shown that module gas-cooled reactors with a total thermal output power of 3 GW in all can produce ∼6 kg of tritium maximum in a year.

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DO - 10.1016/j.fusengdes.2013.05.022

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SP - 2219

EP - 2222

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

SN - 0920-3796

IS - 9-10

ER -

Evaluation of tritium production rate in a gas-cooled reactor with continuous tritium recovery system for fusion reactors

Abstract

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