Oxide particle size distribution from shearing irradiated and unirradiated LWR fuels in Zircaloy and stainless steel cladding :
significance for risk assessment /
W. Davis, Jr., G.A. West, R.G. Stacy ; prepared for the U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Division of Fuel Cycle and Material Safety ; prepared by the Oak Ridge National Laboratory for the Department of Energy.

Description

Main Author

Davis, W. (Wallace), 1918-

Related Names

Stacy, R. G., author.
West, G. A., author.
United States. Department of Energy.
Oak Ridge National Laboratory. Chemical Technology Division.
U.S. Nuclear Regulatory Commission. Division of Fuel Cycle and Material Safety.

Language(s)

English

Published

Washington, D. C. : Division of Fuel Cycle and Material Safety, 1979.

Subjects

Nuclear fuels.
Nuclear fuel claddings > Nuclear fuel claddings / Effect of radiation on.
Zircaloy-2 > Zircaloy-2 / Effect of radiation on.
Nuclear fuel claddings > Nuclear fuel claddings / Effect of radiation on.
Nuclear fuels.

Note

Manuscript completed Mar. 22, 1979; published Oct. 1979.
Interagency agreement DOE 40-549-75; NRC FIN No. B0102.
At head of title: Contract No. W-7405-eng-26, Chemical Technology Division.

Physical Description

iii, 40 pages : illustrations ; 28 cm.

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