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Title: Swelling, microstructural development and helium effects in type 316 stainless steel irradiated in HFIR and EBR-II

Conference ·
OSTI ID:6303591

This work examines the swelling and microstructural development of a single heat of 20%-cold-worked type 316 stainless steel irradiated to produce displacement damage and a high, continuous helium generation rate, in the High Flux Isotope Reactor (HFIR). Similar irradiation of the same heat of steel in the Experimental Breeder Reactor (EBR)-II is used as a base line for comparing displacement damage accompanying a very low continuous helium generation rate. At temperatures above and below the void swelling regime (approx. 350 to 625/sup 0/C) swelling is greater in HFIR than in EBR-II. In the temprature range of 350 to 625/sup 0/C, cavity formation, precipitation and dislocation recovery are both enhanced and accelerated in HFIR, often causing swelling at lower dose than in EBR-II. In HFIR, however, cavities appear to be bubbles rather than voids. They are about 10 times smaller and 20 to 50 times more numerous than voids in EBR-II. Thus, the swelling becomes greater in EBR-II than in HFIR for 20%-CW 316 in the void swelling temperature ranges as fluence increases. Such differences in swelling and microstructural behavior must be understood in order to anticipate the behavior of materials during fusion irradiation.

Research Organization:
Oak Ridge National Lab., TN (USA)
DOE Contract Number:
W-7405-ENG-26
OSTI ID:
6303591
Report Number(s):
CONF-810831-29; ON: DE81028603; TRN: 81-015221
Resource Relation:
Conference: Fusion reactor materials meeting, Seattle, WA, USA, 9 Aug 1981
Country of Publication:
United States
Language:
English