Oxidative Decladding of Uranium Dioxide Fuels
作者:
BodineJ. E.,
GroceI. J.,
GuonJ.,
HansonL. A.,
期刊:
Nuclear Science and Engineering
(Taylor Available online 1964)
卷期:
Volume 19,
issue 1
页码: 1-7
ISSN:0029-5639
年代: 1964
DOI:10.13182/NSE64-A19784
出版商: Taylor&Francis
数据来源: Taylor
摘要:
AbstractThe oxidative decladding of UO2fuels has been demonstrated on three-foot sections of unirradiated fuel rods and on eight-inch sections of fuel rods irradiated to 21,000 MWd/MTU.Decladding rates were unaffected by the extent of irradiation. Uranium dioxide which was unirradiated, irradiated, and with fissia added to simulate 100,000 MWd/MTU irradiation was declad at similar rates. The effect of pressure and temperature on decladding rates was determined. Puncturing the cladding greatly enhanced the rate and gave a coarser product. This product was not completely converted to U3O8during oxidative decladding.Greater than 99.9% of the UO2fuel was removed from the cladding. There was no detectable contamination of the product by the cladding material. Little or no fission-product or plutonium decontamination was observed. Dissolution rates for the declad product, in 50% nitric acid, were 20 times as fast as for the“as received”UO2fuel.
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