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Conference Article: Development of the graphite matrix materials of the fuel elements for the 10 MW HTR test module

Qiu Xueliang; He Jun; Guo Guiju; Zuo Kaifer; Zhang Shuangxi (Tsinghua Univ., Beijing (China). Inst. of Nuclear Energy Technology)

Abstract

The development of the graphite matrix materials of the spherical fuel elements for the 10MW HTR Test Module began from 1988. Semi-isostatic cold-molding with silicon rubber die is used in the manufacture of the spherical fuel elements. A kind of matrix material similar to A3-3 was developed. The properties of the matrix materials are determined, and approach the level of A3-3. Irradiation tests are planned to carry out. It is underway to improve the corrosion-resistance of the matrix, or to develop a corrosion-resistance fuel element.

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key words: Gas Cooled Reactor, Nuclear Technology
Reference:
Specialists meeting on graphite moderator lifecycle behaviour. Bath (United Kingdom). 24-27 Sep 1995.
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--901, pp:341-349