EXAMINATION OF PWR CORE 1 BLANKET FUEL RODS FOR MICROSTRUCTURE, HYDROGEN PICKUP AND BURST STRENGTH
Technical Report
·
OSTI ID:4072458
Three investigations were performed upon natural UO/sub 2/ fuel rods removed from the PWR blanket after 5800 efph of operation. Microexamination of the fuel revealed no radiation-induced changes, while the microstructures of the Zircaloy cladding and end caps showed modest amounts of uniformly distributed hydride. Hydrogen analysis of the Zircaloy indicated about 50 to 100 ppm. Hydraulic pressures of 13,200 to 14,900 psi were required for bursting of the rods. These results indicate that the rods are suitable for continued service. (auth)
- Research Organization:
- Westinghouse Electric Corp. Bettis Atomic Power Lab., Pittsburgh
- DOE Contract Number:
- AT(11-1)-GEN-14
- NSA Number:
- NSA-15-013257
- OSTI ID:
- 4072458
- Report Number(s):
- WAPD-TM-264
- Country of Publication:
- United States
- Language:
- English
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