Post-irradiation examination of in-pile stress-rupture specimens (ORR S-2 and ORR S-3)
Description:
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 n…
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Date:
September 29, 1967
Creator:
Johnson, L. L.
Item Type:
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Report
Partner:
UNT Libraries Government Documents Department