Feasibility of and methodology for thermal annealing an embrittled reactor vessel. Volume 1. Program overview. Final report. [PWR; BWR]

Technical Report · Sat Jan 01 04:00:00 EST 1983

OSTI ID:6470537

Mager, T R

An EPRI sponsored program was carried out by Westinghouse to determine the extent of fracture toughness recovery as a function of annealing time and temperature for neutron embrittlement sensitive reactor vessel material and to develop an optimal thermal anneal procedure for field applications. Program materials were three weldments fabricated by Combustion Engineering, Inc., from the same heat of A533 Grade B Class 1 plate material and the same heat of MnMoNi weld wire. The only variables were the target copper level and the welding flux which was Linde Grade 80 and Linde 0091. Weldments of 0.22, 0.36, and 0.41 wt % copper were produced. It was concluded from this study that excellent recovery of all properties could be achieved by annealing at 850/sup 0/F (454/sup 0/C) and above for 168 hours. Such an annealing resulted in ductile-brittle transition temperature shift recovery of 80 to 100%, and reirradiation after this annealing indicated that the ductile-brittle transition temperature shift appears to continue at the rate which would have been expected had no anneal been performed. System limitations were identified for both wet and dry annealing methods.

• Research Organization: Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear Technology Div.
• OSTI ID: 6470537
• Report Number(s): EPRI-NP-2712-Vol.1; ON: DE83901589
• Country of Publication: United States
• Language: English

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