MOX fuel irradiation behavior in steady state (irradiation test in HBWR) (summary)

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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 behavior for thermal reactor. objective of irradiation tests is to investigate fuel behavior 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-irradiation examination. The following observations are made. (1) PNC MOX fuels have achiived high burn-up as 57Gwd/t MOX (65Gwd/tm) at pellet peak without failure. (2) there

使用言語	:	English
掲載資料名	:	Proceedings of International Topical Meeting on Light Water Reactor Fuel Performance
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ページ数	:	0 Pages
発行年月	:	1994/07
発表会議名	:	ANS International Topical Meeting on Light Water Reactor Fuel Performance
開催年月	:	1994/04
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登録番号 : 08-1993-0028
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