National Technical Reports Library

The National Technical Information Service acquires, indexes, abstracts, and archives the largest collection of U.S. government-sponsored technical reports in existence. The NTRL offers online, free and open access to these authenticated government technical reports. Technical reports and documents in its repository may be available online for free either from the issuing federal agency, the U.S. Government Publishing Office’s Federal Digital System website, or through search engines.

Details

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

DE2001768605

Publication Date	2001
Personal Author	Finn, P. A.; Tsai, Y.; Goldberg, M. M.; Strain, R. V.
Page Count	10
Abstract	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.
Keywords	Mixed oxide fuels Fuel pins Spent fuels Fission products Actinides Irradiation Gradients Grain boundaries Nuclides Corrosion
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Argonne National Lab., IL.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200122

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

(129)I Release Fractions in Unsaturated Tests with Fast-Flux MOX Fuels.
DE2001768605

Publication Date	2001
Personal Author	Finn, P. A.; Tsai, Y.; Goldberg, M. M.; Strain, R. V.
Page Count	10
Abstract	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.
Keywords	Mixed oxide fuels Fuel pins Spent fuels Fission products Actinides Irradiation Gradients Grain boundaries Nuclides Corrosion
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Argonne National Lab., IL.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200122