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1987 Fiscal Year Final Research Report Summary

Study on characterization of ceramic materials for nuclear engineering

Research Project

Project/Area Number 61470161
Research Category

Grant-in-Aid for General Scientific Research (B)

Allocation TypeSingle-year Grants
Research Field Nuclear engineering
Research InstitutionUniversity of Tokyo

Principal Investigator

TAKAHASHI Yoichi  Professor, University of Tokyo, 工学部, 教授 (90010735)

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)
Project Period (FY) 1986 – 1987
KeywordsCeramics / Porosity / Tritium breeding / Asdorption / Lithium compounds / Equilibrium pressure / Permeatiion / トリチウムインベントリー
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.

  • Research Products

    (4 results)

All Other

All Publications (4 results)

  • [Publications] Takayuki Terai et al.: Journal of Nuclear Science and Technology.

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] Haruki Mdarame et al.: Fusion Engineering and Design.

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] Takayuki Terai et al.: "A conceptual design of RFP fusion power reactor - REPUTER-I" Journal of Nuclear Science and Technology.

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] Haruki Madarame et al.: "Tritium mugration resistance in solid blanket of fusion reactor" Fusion Engineering and Design.

    • Description
      「研究成果報告書概要(欧文)」より

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Published: 1989-03-30  

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