Feasibility of and Methodology for Thermal Annealing an Embrittled Reactor Vessel Volume 2:Detailed Technical Descriptionnof the Work

摘要

An EPRI sponsored program was carried out by Westinghouse to determine the extent of fracture tough¬ness 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 mate¬rials 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 Mn Mo Ni 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 weight percent copper were produced.nSpecimens fabricated from the three submerged arc weldments included Type A Charpy V-notch impact, small size tensile, and 1 /2T compact tension specimens. After encapsulation, the specimens were irradiat¬ed at the University of Virginia Research Reactor to two fluence levels, 8 x 1018 n/cm2 and 1.5 x 10^ n/cm2 (E > 1 MeV).