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U.S. Department of Energy
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FISSION-PRODUCT RELEASE FROM FUEL-ELEMENT CLADDINGS. Quarterly Progress Report for October-December 1963

Technical Report ·
OSTI ID:4083211
Postirradiation heating experiments to study Xe/sup 133/ release from foils of iron-20 wt% chromium-alloy specimens impregnated with fission recoils showed that release is time, temperature, and concentration dependent. An activation energy of 36 kcal per mole is associated with an initial rapid or burst release component while a lower activation energy of 20 kcal per mole appears to be associated with a slower long-time release component. The rate of release is concentration dependent in both components. The gas-release behavior is apparently strongly influenced by gas-bubble formation. In postirradiation heating experiments to measure release of Xe/sup 133/ through material unaffected by fission recoils, no measurable release is observed. Thus, unless irradiation affects the gasdiffusion behavior, significant release by diffusion through the cladding of a fuel element would not be expected. In solid-fission-product studies diffusion coefficients are determined at 600, 800, 1000, and 1200 deg C for a concentration of 2 x 10/sup -5/ recoils per cm/sup 2/. Diffusion coefficients and activation energies for molybdenum, ruthenium, and highdiffusion- rate components of tellurium and zirconium are about the same as that for the diffusion of chromium in stainless steel. Cerium, barium, iodine, and the slower zirconium component give noticeably lower diffusion coefficients and activation energies. (auth)
Research Organization:
Battelle Memorial Inst., Columbus, Ohio
DOE Contract Number:
W-7405-ENG-92
NSA Number:
NSA-18-010522
OSTI ID:
4083211
Report Number(s):
BMI-X-10072; EURAEC-936
Country of Publication:
United States
Language:
English