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Title: Reactor vessel material surveillance program

Technical Report ·
OSTI ID:4380877

B&W conducts surveillance programs for its 850-MW(e) class of reactors to determine the effects of neutron irradiation on the full Charpy V-notch curves of the reactor vessel materials. Charpy and tensile specimens, which are machined from as-fabricated metal, heat-affected-zone metal (HAZ), and weld metal, are placed in six surveillance capsules containing dosimeters and temperature monitors. The capsules are then placed in three holder tubes, which are positioned so that the capsules are near the peak axial neutron flux. In the Oconee 1 and Three Mile Island 1 plants, two thermal aging capsules have been placed in an area of essentially zero flux. In the remainder of the 850-MW(e) class plants, thermal aging boxes will contain specimen plates of reactor-vessel materials. The flux level at the box location will be practically zero. However, the thermal environment at the box location between the vessel upper head and the insulation will be almost identical to that of the surveillance capsule. These specimen plates will be available for future use as thermally aged specimens. The holder tubes are attached to the thermal shield and can be installed and removed along with the internals core support assembly. Once the internals are installed, the holder tubes are rotated toward the vessel's wall and locked in place at favorable locations for irradiation of the specimens. Calculations indicate that B&W's method is a reliable, conservative means of predicting peak neutron fluence. (auth)

Research Organization:
Babcock and Wilcox Co., Lynchburg, Va. (USA). Nuclear Power Generation Dept.
NSA Number:
NSA-29-008343
OSTI ID:
4380877
Report Number(s):
BAW-10006(Rev.3)
Resource Relation:
Other Information: Orig. Receipt Date: 30-JUN-74
Country of Publication:
United States
Language:
English