Mitigating IASCC of Reactor Core Internals by Post-Irradiation Annealing
- Univ. of Michigan, Ann Arbor, MI (United States)
This final report summarizes research performed during the period between September 2012 and December 2016, with the objective of establishing the effectiveness of post-irradiation annealing (PIA) as an advanced mitigation strategy for irradiation-assisted stress corrosion cracking (IASCC). This was completed by using irradiated 304SS control blade material to conduct crack initiation and crack growth rate (CGR) experiments in simulated BWR environment. The mechanism by which PIA affects IASCC susceptibility will also be verified. The success of this project will provide a foundation for the use of PIA as a mitigation strategy for core internal components in commercial reactors.
- Research Organization:
- Univ. of Michigan, Ann Arbor, MI (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE). Nuclear Energy University Programs (NEUP)
- DOE Contract Number:
- AC07-05ID14517
- OSTI ID:
- 1363766
- Report Number(s):
- DOE/NEUP-12-3430; 12-3430; TRN: US1702246
- Country of Publication:
- United States
- Language:
- English
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