| Project Area | Tritium Science and Technology for Fusion Reactor |
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| Project/Area Number |
19055002
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| Research Category |
Grant-in-Aid for Scientific Research on Priority Areas
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| Allocation Type | Single-year Grants |
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| Review Section |
Science and Engineering
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| Research Institution | University of Toyama |
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Principal Investigator |
HATANO Yuji 富山大学, 水素同位体科学研究センター, 教授 (80218487)
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| Co-Investigator(Kenkyū-buntansha) |
TORIKAI Yuji 富山大学, 水素同位体科学研究センター, 准教授 (80313592)
AKAMARU Satoshi 富山大学, 水素同位体科学研究センター, 助教 (10420324)
OYA Yasuhisa 静岡大学, 理学部, 准教授 (80334291)
ODA Takuji 東京大学, 大学院・工学系研究科, 助教 (40436556)
TANAKA Satoru 東京大学, 大学院・工学系研究科, 教授 (10114547)
NAKAMURA Hirofumi 日本原子力研究開発機構, 核融合研究開発部門, 研究主幹 (20354615)
ASAKURA Yamato 核融合科学研究所, ヘリカル研究部, 教授 (00342642)
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| Project Period (FY) |
2007 – 2011
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| Project Status |
Completed (Fiscal Year 2011)
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| Budget Amount *help |
¥114,700,000 (Direct Cost: ¥114,700,000)
Fiscal Year 2011: ¥8,100,000 (Direct Cost: ¥8,100,000)
Fiscal Year 2010: ¥20,000,000 (Direct Cost: ¥20,000,000)
Fiscal Year 2009: ¥24,400,000 (Direct Cost: ¥24,400,000)
Fiscal Year 2008: ¥32,400,000 (Direct Cost: ¥32,400,000)
Fiscal Year 2007: ¥29,800,000 (Direct Cost: ¥29,800,000)
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| Keywords | 核融合 / トリチウム / 水素 / 放射性同位体 / 放射線 / 同位体効果 / 透過 / 除染 |
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| Research Abstract |
The objective of this study is to gain an understanding of tritium (T)-material interactions to minimize uncontrolled tritium emissions from fusion reactors. The main chemical forms of T permeating steel pipes are HT and HTO, and the latter has a far higher risk of internal exposure. We found that the fraction of HTO was able to be reduced by reducing surface coverage of Fe hydroxides. Developments of wet-chemical methods to prepare ceramic permeation barrier coatings enabled reduction in permeation rate to 1/104. Retention of T in tungsten being a leading candidate of plasma-facing material was found to increase significantly with neutron irradiations. Important parameters for assessment of T inventory in a reactor core such as binding energy between T and radiation defects were quantitatively evaluated. Heat treatments under the presence of H and/or D were proposed for efficient decontamination of neutron-irradiated tungsten.
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