Study on characterization of ceramic materials for nuclear engineering
| Project/Area Number |
61470161
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| Research Category |
Grant-in-Aid for General Scientific Research (B)
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| Allocation Type | Single-year Grants |
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| Research Field |
Nuclear engineering
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| Research Institution | University of Tokyo |
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Principal Investigator |
TAKAHASHI Yoichi Professor, University of Tokyo, 工学部, 教授 (90010735)
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| Co-Investigator(Kenkyū-buntansha) |
NAMBA Takashi Research associate, University of Tokyo, 工学部, 助手 (20133100)
YONEOKA Toshiaki Research associate, University of Tokyo, 工学部, 助手 (40013221)
TERAI Takayuki Associate professor, University of Tokyo, 工学部, 助教授 (90175472)
TANAKA Satoru Associate professor, University of Tokyo, 工学部, 助教授 (10114547)
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| Project Period (FY) |
1986 – 1987
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| Project Status |
Completed (Fiscal Year 1987)
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| Budget Amount *help |
¥4,800,000 (Direct Cost: ¥4,800,000)
Fiscal Year 1987: ¥1,000,000 (Direct Cost: ¥1,000,000)
Fiscal Year 1986: ¥3,800,000 (Direct Cost: ¥3,800,000)
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| Keywords | Ceramics / Porosity / Tritium breeding / Asdorption / Lithium compounds / Equilibrium pressure / Permeatiion / トリチウムインベントリー / 多孔質 / 焼結体 / 気体透過率 / 相互拡散係数 / フッ化リチウム / 核融合炉ブランケット / トリチウム増殖材 |
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| Research Abstract |
Ceramic materials are very important in nuclear engineering. They have such complicated textures that gas transport process through them is not easy to understand. The aim of this study was to measure the structure and the characterisitics of adsorption and the gas permeation in order to clarify the relationship among them on fusion reacter blanket materials.
This study was performed in the following themes:
1. Gas permeability and pore structure of sintered lithium fluoride(LiF).
As a system having weak interaction between permeating gas and sintered matrix, a pair of LiF and Ar-He gas mixture was chosen, and the gas permeability and the diffusity through LiF samples prepared in various sintering condition. It was shown that they can be expressed by a simple function of porosity in the matrix determined by a mercury porosimeter.
2. Adsorption of H_2O on Li_2O and equilibrium vapor pressure of H_2O in the system of Li_2O-LiOH mixture.
Adsorption amount of H_2O on lithium oxide (Li_2O) samples with various sizes of apparent particle radius as well as its enthalpy change was measured to investigate the chemical interaction of permeating gas and sintered matrix. In addition, equilibrium vapor pressure of H_2O in the system of Li_2O-LiOH mixture was obtained in high accuracy in the wide temperature range of 350-620゜c.
3. Estimation of tritium inventory in fusion reactor blanket.
Computational code to calculate tritium transport in fusion reactor blanket was constructed in order to estimate the tritium inventory of RFP- type fusion reactor. In this code, some data obtained in this study swre utilized, and its availability and importance were recognized.
The final report on this project has been published.
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Report
(2 results)
Research Products
(5 results)
