PERFORMANCE OF HT9 CLAD METALLIC FUEL AT HIGH-TEMPERATURE

[摘要] Irradiation testing and post-irradiation examination of HT9 clad U-10Zr metallic fuel has been carried out in the EBR-II reactor. Peak cladding temperatures in the range of 630 to 660-degrees-C were obtained in order to study high temperature breach behavior of metallic fuel. Of the 15 experimental fuel elements tested to 10 at% burnup, two breached by stress rupture. Breach behavior was found to be totally benign for reactor operations. Significant fuel/cladding chemical interactions involving lanthanide-series fission products and carbide depletion were observed in the hottest cladding region.

[发布日期] 1993-09-01

[效力级别]  Proceedings Paper