MOX fuel irradiation behaviour in steady state (irradiation test in HBWR) (fuel paper)

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not registered; not registered; Kamimura, Katsuichiro

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Two rigs of plutonium-uranium mixed oxide (MOX) fuel rods have been irradiated in halden boiling water reactor (HBWR) to investigate MOX fuel behaviour for thermal reactor. objective of irradiation tests is to investigate fuel behaviour as influenced by pellet shape, pellet surface treatment, pellet-cladding gap size and mox fuel powder preparation process. The two rigs have instrumentations for in-pile measurements of the fuel center-line temperature, plenum pressure, cladding elongation and fuel stack length change. The data taken through in-operation instrumentations have been analyzed and compared with those from post-irradiationexamination. The following observations are made. (1) pnc mox fuels have achived high burn-up as 59Gwd/t MOX (67Gwd/t m) at pellet peak without failure. (2) th

使用言語	:	English
掲載資料名	:	Int. Topical Meeting on LWR Fuel Performance
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ページ数	:	0 Pages
発行年月	:	1994/04
発表会議名	:	Int.Topical Meeting on LWR Fuel Performance
開催年月	:	1994/04
開催都市	:	South Florida
開催国	:	U.S.A
キーワード	:	no keyword

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