Review on effect of cyclic loading on environmental assisted cracking of alloy 600 in typical nuclear coolant waters
Source abstract
Abstract
Abstract Corrosion fatigue data for alloy 600 in simulated primary side, pressurised water reactor (PWR) coolant and in oxygenated pure water (OPW) have been reviewed. Higher crack growth rates occur in these environments than in air and the former show a dependence upon frequency of loading, ν , and R ratio. The d a /d N versus ΔK plots have a tendency to show plateau regions where d a /d N remains constant with increasing ΔK . The enhancements of crack growth over those in air due to cyclic loading are larger in OPW than in simulated PWR primary side water. If corrosion fatigue of alloy 600 was perceived of importance for reactor components, the existing data base will need to be extended and it would be necessary to generate more air fatigue data than is currently available. Conventional S – N fatigue and corrosion fatigue data from smooth surface specimens may also be required, collected taking due regard of the possible effects of R and ν mentioned above.
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Research context
OpenAlex topics: Fatigue and fracture mechanics · Nuclear Engineering Thermal-Hydraulics · Non-Destructive Testing Techniques
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (34)
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