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An investigation of steady-state radiation embrittlement of reactor vessels, which consists of surveillance capsule supplemental testing and mechanistic studies, is being conducted by the Westinghouse Electric Corporation for the Electric Power Research Institute. A summary of the increases in the 41-J (30-ft · lb) transition temperature exhibited by submerged arc weld material contained in eight supplemental surveillance capsules included in this investigation is presented. The data indicate that radiation damage for high-copper submerged arc welds does not saturate but does tend to show a very low rate of embrittlement at neutron fluences greater than ∼1 × 1019 n/cm2. The data also indicate that radiation damage predictions based on U.S. Nuclear Regulatory Guide 1.99, Revision 1, are not realistic for fluences greater than ∼1 × 1019 n/cm2, for most pressure vessel steels.
radiation embrittlement, pressure vessel material, radiation damage saturation, steady-state embrittlement, high-copper submerged arc welds 8, E0185
Manager, Metallurgical and Nondestructive Analysis, Nuclear Technology Division, Westinghouse Electric Corporation, Pittsburgh, Pa.
Project Manager, Electric Power Research Institute, Palo Alto, Calif.
Senior Engineer, Nuclear Technology Division, Westinghouse Electric Corporation, Pittsburgh, Pa.