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Iyoku, Tatsuo; Takikawa, Noboru; Shiozawa, Shusaku; Sawa, Kazuhiro; Tsuji, Masanobu; Yamada, Kunitaka; Sugihara, Tetsuya.
Japan Atomic Energy Research Inst., Tokyo (Japan)1993
Japan Atomic Energy Research Inst., Tokyo (Japan)1993
AbstractAbstract
[en] The graphite inspection standard for the High Temperature Engineering Test Reactor (HTTR) consists of material, nondestructive, dimensional and visual inspections. The inspection method and judgement criteria in the material inspection are nor detailed in some items, although some explanations are provided for the items especially necessary to be considered in the inspection. Therefore, inspection method and judgement criteria in the material inspection which contains material grade, impurity and mechanical strength inspections, are fully evaluated on the basis of the feature of these materials. Material inspection method and judgement criteria for HTTR graphite and carbon are evaluated in consideration of the research data and manufacturing experiences. As a result, inspection method and judgement criteria can be established, which are to be applied to the graphite and carbon internal acceptance tests of HTTR. (author)
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Jan 1993; 33 p
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