Experimental Investigation of Multicycle Irradiation and Annealing Effects on Notch Ductility of A533-B Weld Deposits / JR. Hawthorne, HE. Watson, FJ. Loss
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- Postirradiation heat treatment (annealing) at 399¿̐ưC has demonstrated a capability for the relief of radiation embrittlement to reactor vessel steels. Building on an earlier investigation, this report describes a study of Charpy-V (CV) notch ductility and tensile properties behavior of two representative reactor vessel welds under cyclic 399¿̐ưC postirradiation annealing and 288¿̐ưC reirradiation. The welds were by the submerged-arc process and were chosen for their high radiation sensitivity (high copper content) and for their difference in as-fabricated CV upper-shelf energy levels derived from different welding fluxes. Weld properties were determined at each phase of the anneal-reirradiation-reanneal-reirradiation sequence.
- Dates of Publication and/or Sequential Designation:
- Volume 1981, Issue 725 (January 1981)
- 9780803147942 (e-ISBN)
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- Includes bibliographical references 5.
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- Electronic reproduction. W. Conshohocken, Pa. : ASTM International, 1981. Mode of access: World Wide Web. System requirements: Web browser. Access may be restricted to users at subscribing institutions.
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