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.
Main Author: | Davis, W. 1918- |
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Related Names: | Stacy, R. G. , author., West, G. A. , author. |
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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Item Link | Original Source |
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Full view | Technical Report Archive & Image Library |