Post-irradiation examination of in-pile stress-rupture specimens (ORR S-2 and ORR S-3) [electronic resource].

Published: Canoga Park, Calif : North American Aviation, inc. Atomics International Division, 1967.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Additional Creators: North American Aviation. Atomics International Division and United States. Department of Energy. Office of Scientific and Technical Information

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Summary

Hastelloy-N fuel cladding tube specimens were stress-rupture-tested in-pile at the Oak Ridge National Laboratory. Two cladding heats were tested at 1400/sup 0/F; hoop stresses ranged from 8000 psi to 26,000 psi. The tubes were then shipped to the Atomics International Hot Laboratory where cladding visual examination, dimensional measurement, and metallographic analysis were performed. Average cladding creep ductility was 1.2%. Cladding failures were intergranular, with some secondary cracking noted. Both cladding ductility and rupture life were reduced by irradiation.

Report Numbers

E 1.99:naa-sr-tdr-12577
naa-sr-tdr-12577

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Note

Published through SciTech Connect.
09/29/1967.
"naa-sr-tdr-12577"
"DE85004470"
Johnson, L.L.

View MARC record | catkey: 14463725