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Void-Precipitate Association During Neutron Irradiation of Austenitic Stainless Steel Pages: 34 Published: Jan 1987
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View License Agreement Source: STP955-EB Abstract Microstructural data have recently become available on a single heat of 316 stainless steel irradiated in EBR-II and HFIR, over a wide range of irradiation temperatures (55 to 750°C), doses (7 to 75 dpa), and several helium generation rates (0.5 to 55 atomic ppm He/dpa). Results on just one heat of steel minimize effects that may be related to compositional differences. In this work we present these data in order to offer a characterization of precipitate-void association within the context of the overall microstructural evolution. Observations on a second heat of steel are also presented here to allow us to assess which microstructural correlations are general. The analysis of experimental results leads us, first, to conclude that precipitate-void association is not only dependent upon local conditions at the precipitate interface but is also strongly related to the overall microstructural evolution. Second, we suggest a precipitation mechanism that helps to understand precipitate-void codevelopment. Keywords: swelling, neutron irradiation, austenitic stainless steels, microstructure, phase stability, radiation induced segregation, voids, precipitation, helium effects Paper ID: STP33816S Committee/Subcommittee: E10.07 DOI: 10.1520/STP33816S ASTM International is a member of CrossRef. | ||