Postirradiation examination results for the Irradiation Effects Test Series IE-ST-2, Rod IE-002. [PWR]

Technical Report · Wed Nov 30 23:00:00 EST 1977

DOI:https://doi.org/10.2172/5196362· OSTI ID:5196362

Murdock, B. A.

A postirradiation examination was conducted on a zircaloy-clad, UO/sub 2/-fueled, pressurized water reactor (PWR) type rod which had been tested in the Power Burst Facility as part of the Irradiation Effects Test Series of the Thermal Fuels Behavior Program. The fuel rod, previously irradiated to a burnup of 15,800 MWd/t was subjected to a power ramp from 28 to 55 kW/m peak power at an average ramp rate of 4 kW/m/min. Posttest fuel restructuring and relocation, fission product redistribution, and fuel rod cladding deformation were evaluated and analyzed.

• Research Organization: SEE CODE- 9502158 EG and G Idaho, Inc., Idaho Falls (USA). Idaho National Engineering Lab.
• OSTI ID: 5196362
• Report Number(s): TREE-NUREG-1177
• Country of Publication: United States
• Language: English

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