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MOX Fuel Performance Experiment Specified for Japanese PWR Utilisation in the HBWR

2006; Taylor & Francis; Volume: 43; Issue: 9 Linguagem: Inglês

10.1080/18811248.2006.9711188

1881-1248

Hajime FUJII, Hideyuki Teshima, Katsumasa Kanasugi, Toshikazu SENDO,

Nuclear and radioactivity studies

In order to obtain high burn-up MOX fuel irradiation performance data, SBR and MIMAS MOX fuel rods with Pufissile enrichment of about 6 wt% have been irradiated in the HBWR. In-pile performance data of MOX have been obtained, and the peak burn-up of MOX pellet have reached to 66 GWd/tM as of October 2004. MOX fuel temperature is confirmed to have no significant difference compared to UO2, if taking into account adequately for thermal conductivity degradation due to PuO2 addition and burn-up development, and measured fuel temperature agrees well with HB-FINE code calculation up to high burn-up region. Fission gas release of MOX is possibly larger than UO2 based on temperature and pressure assessment. No significant difference is confirmed between SBR and MIMAS MOX on FGR behaviour. MOX fuel swelling rate agrees well with solid swelling rate. Cladding elongation data shows onset of PCMI in high power region. Ramp test data from other experiment programs with various types of MOX fabrication route confirms superior PCI resistance of MOX compared to UO2, due to enhanced creep rate of MOX. The irradiation is expected to continue until achieving of 70 GWd/tM (MOX pellet peak).