(129)I Release Fractions in Unsaturated Tests with Fast-Flux MOX Fuels.

Finn, P. A. ; Tsai, Y. ; Goldberg, M. M. ; Strain, R. V.

Technical Information Center Oak Ridge Tennessee

关键词: Mixed oxide fuels;    Fuel pins;    Spent fuels;    Fission products;    Actinides;   

RP-ID  :  DE2001768605

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports Library

【 摘 要 】

The Department of Energy (DOE), National Spent Nuclear Fuel Program (NSNFP) has the responsibility to provide the Yucca Mountain Project (YMP) with information on the release of fission products and actinides from DOE spent fuels, which include fast-flux MOX fuel. The nuclide release behavior of two MOX fuel pins, which had high centerline temperatures (210O degrees C) during irradiation and steep temperature gradients across the 3-mm radius of the fuel pin, i.e. from 21OO degrees C to 600 degrees C, are being examined under unsaturated conditions. The high centerline temperature during irradiation resulted in massive grain restructuring with the formation of columnar grains at the center to mid-radius of a pin and equiaxed grains adjacent to the columnar grains.