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

; ; Kamimura, Katsuichiro

Int. Topical Meeting on LWR Fuel Performance, 0 Pages, 1994/04

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