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Exploratory investigations of cyclic irradiation and annealing effects on notch ductility of A533-B weld deposits

Journal Article · · Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)
DOI:https://doi.org/10.1520/STP38171S· OSTI ID:5711227

Postirradiation heat treatment (annealing) is being investigated as a possible method for the periodic relief of radiation embrittlement to reactor vessel steels. This report describes a study of the Charpy-V (C/sub v/) notch ductility of two representative A533-B weld deposits under two full annealing and reirradiation cycles. The welds were specially chosen for their high sensitivity to radiation effects and for their difference in as-fabricated C/sub v/ upper-shelf energy levels. Notch ductility properties were determined at each phase in the irradiation-annealing sequence. Heat-treatment temperatures were selected to represent two heat-treatment options open for vessel annealing. Results demonstrate that a 399/sup 0/C (750/sup 0/F), 168-h heat treatment is highly effective for reducing radiation embrittlement accrual in service; in contrast, a 343/sup 0/C (650/sup 0/F), 168-h heat treatment is shown to be of little benefit for the fluence conditions investigated. A greater rate of radiation embrittlement was observed for the heat-treated material (both conditions) compared with nonheat-treated material. The investigations also revealed a significant difference between upper-shelf energy and transition temperature response to heat treatment.

Research Organization:
Naval Research Lab., Washington, DC
OSTI ID:
5711227
Journal Information:
Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States), Journal Name: Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States) Vol. 683; ISSN ASTTA
Country of Publication:
United States
Language:
English