期刊
MATERIALS SCIENCE & ENGINEERING R-REPORTS
卷 73, 期 7-8, 页码 67-83出版社
ELSEVIER SCIENCE SA
DOI: 10.1016/j.mser.2012.05.002
关键词
Radiation damage; Radiation-induced degradation; Light water reactor; Point defects; Point defect clustering; Transmutation effects; Voids; Swelling; Creep; Radiation-induced segregation; Radiation-induced precipitation; Embrittlement; Radiation hardening; Irradiation-induced stress corrosion cracking
资金
- Oak Ridge National Laboratory by the Light Water Reactor Sustainability Program, Office of Nuclear Energy, U.S. Department of Energy
- ORNL's Shared Research Equipment (ShaRE) User Facility
- Office of Basic Energy Sciences, U.S. Department of Energy
In order to provide a scientific basis for proposed life extension of current light water reactors, the radiation-induced degradation of stainless steel reactor internals will be discussed. A brief review of the basic radiation damage effects in stainless steels at LWR relevant conditions will be presented. It will be discussed how these basic effects result in the key degradation modes that have been identified by light water reactor experience to date, as well as the possibility for more severe degradation or new forms of degradation under extended service conditions. The forms of degradation that will be discussed include radiation hardening, embrittlement, dimensional stability (e.g., creep and swelling), radiation-induced segregation and precipitation, transmutation effects and irradiation-induced stress corrosion cracking. (C) 2012 Elsevier B.V. All rights reserved.
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