A fracture mechanics analysis of the PWR nuclear power plant reactor pressure vessel beltline weld
Source abstract
Abstract
Abstract In this paper, a generic pressured water reactor (PWR) power plant reactor vessel is analyzed. The primary purpose of this work is to assure structural integrity of the irradiated reactor pressure vessel (RPV) beltline weld under normal operating conditions at the end-of-life, as specified by the requirements of 10CFR50, App.G. It is found that suitable margins of safety are maintained at the end-of-life (32 effective full power years or 1.25×10 23 n/m 2 inner wall fluence).
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fatigue and fracture mechanics · Nuclear and radioactivity studies · Nuclear Materials and Properties
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (7)
Show source-provided references
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