Environmental effect of PWR primary water on fatigue life of stainless steel (influence of loading rate on fatigue life reduction)
Source abstract
Abstract
Abstract Fatigue tests on Type 316 stainless steel specimens were conducted for various combinations of rise time and strain range in simulated pressurized water reactor (PWR) water. It was demonstrated that crack growth rate estimated from test results correlated well with the strain intensity factor range. An equation for predicting Fen was obtained as a function of rise time and strain range. It was found that, although Fen depends on strain range, the magnitude of the change in Fen due to the strain range is negligibly small compared with the scatter in the test results.
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Research context
OpenAlex topics: Fatigue and fracture mechanics · Hydrogen embrittlement and corrosion behaviors in metals · Material Properties and Failure Mechanisms
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
Affiliations
Institute of Nuclear Safety System, Inc. 64 Sata, Mihama‐cho, Mikata‐gun Fukui 919‐1205 Japan
References (33)
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