The Influence of DPA Rate on Void Swelling of Russian Austenitic Stainless Steels
Void swelling of PWR austenitic internals has recently been identified as a materials issue that might impact license extension. Earlier published studies have shown that the atomic displacement rate is unexpectedly one of the most important variables that determine the magnitude of swelling. In addition to differences in neutron spectra, light water reactors operate at displacement rates that are significantly lower than those of typical fast reactors, leading to considerable uncertainty in the extrapolation of fast reactor data to light water reactor conditions. This paper presents new data derived from irradiations conducted on Russian austenitic steels irradiated in a variety of Russian reactors. These data support the conclusion that lowering the dpa rate in general accelerates the onset of swelling in austenitic steels.
- Research Organization:
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC05-76RL01830
- OSTI ID:
- 860062
- Report Number(s):
- PNWD-SA-6198; TRN: US0504849
- Resource Relation:
- Conference: 11th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 82; American Nuclear Society,La Grange Park,,United States.
- Country of Publication:
- United States
- Language:
- English
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