2011 Fiscal Year Final Research Report
Studies on effect of high concentration tritiated water and organic compounds on tritium confinement
| Project Area | Tritium Science and Technology for Fusion Reactor |
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| Project/Area Number |
19055009
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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 | Japan Atomic Energy Agency |
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Principal Investigator |
YAMANISHI Toshihiko 独立行政法人日本原子力研究開発機構, 核融合研究開発部門, 研究主席 (30354616)
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| Co-Investigator(Kenkyū-buntansha) |
HAYASHI Takumi 独立行政法人日本原子力研究開発機構, 核融合研究開発部門, 研究主幹 (70354678)
IWAI Yasunori 独立行政法人日本原子力研究開発機構, 核融合研究開発部門, 研究主幹 (70354610)
ISOBE Kanetsugu 独立行政法人日本原子力研究開発機構, 核融合研究開発部門, 研究副主幹 (00354613)
HARA Masanori 富山大学, 水素同位体科学研究センター, 准教授 (00334714)
SUGIYAMA Takahiko 名古屋大学, 大学院・工学研究科, 准教授 (90353440)
OKUNO Kenji 静岡大学, 理学部・付属放射化学研究施設, 教授 (80293596)
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| Co-Investigator(Renkei-kenkyūsha) |
OYAIDSU Makoto 独立行政法人日本原子力研究開発機構, 核融合研究開発部門, 任期付研究員 (60516855)
SATOU Katsumi 独立行政法人日本原子力研究開発機構, 核融合研究開発部門, 技術開発協力員
VLADIMIR Alimov 独立行政法人日本原子力研究開発機構, 核融合研究開発部門, リサーチフェロー
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| Project Period (FY) |
2007 – 2011
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| Keywords | トリチウム / 水処理 / 材料 / 腐食 / 透過 |
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| Research Abstract |
The effect of tritium water on the corrosion behavior of metal materials has been studied. It was found that hydrogen was produced by the corrosion reaction at the metal surface, and the hydrogen diffused into the metal. In the case where tritium is in water, the formation of a protective film against the corrosion was prohibited: larger amount of oxygen dissolved in water is required to form the film. The durability of polymer membrane of electrolyze of WDS (Water Detritiation System) has been studied. No major change in strength of the membrane was observed up to 1000 kGy irradiation by beta ray. The strength of the membrane was decreased by immersing it into tritium water. This behavior could not be ascribed to the effect of radicals by radiological reaction of tritium water. A hydrophobic catalyst has been tested for oxidation of tritium and organic tritium. A set of basic experiment of the oxidize reaction has been carried out. A series of tests of chemical exchange column of WDS has been carried out. A separation factor of 19200 was obtained for H-T system (packed height: 100 cm, flow rate of hydrogen: 5000 cc/min). A simulation code of the column has also been successively developed. Some analytical studies have been carried out by using this code. The behavior of tritium water vapor in some organic materials has been studied. The activation energy of permeation, diffusion, and enthalpy of dissolution were -5.0 kJ/mol, 29 kJ/mol, and -34 kJ/mol for polyimide; 5.2 kJ/mol, 41 kJ/mol, and -36 kJ/mol for cellulose; 10 kJ/mol, 40 kJ/mol, and -30 kJ/mol for polypropylene. It was found that hydrogen was trapped in a oxidize film at stainless steel surface and its bulk. The hydrogen trapped was released by heating the stainless steel, and the release behavior was affected by the decomposition of the film.
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[Presentation] Permeation behaviors of tritium through a type 316 stainless steel2011
Author(s)
Y. Oya, , M. Kobayashi, J. Osuo, M. Suzuki, H. Akiko, K. Matsuoka, Y. Hatano, M. Matsuyama, T. Hayashi, T. Yamanishi, K. Okuno
Organizer
10th International Symposium on Fusion Nuclear Technology (ISFNT-10)
Place of Presentation
Red Lion Hotel、ポートランド(アメリカ合衆国)
Year and Date
20110911-16
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