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Reactor Pressure Boundary Integrity Issues for Pressurized Water Reactors
Reactor Pressure Boundary Integrity Issues for Pressurized Water Reactors
Several instances of primary water stress corrosion cracking (PWSCC) of nickel based alloys have been reported in the reactor pressure boundaries of pressurized water reactors (PWRs). The NRC is investigating the effect of PWSCC on the structural integrity of reactor pressure boundaries at all U.S. PWRs. NRC regulatory actions for Reactor Pressure Vessel (RPV) Upper Head, RPV Bottom Head, the Pressurizer, Reactor Coolant Systems Welds, and Overview are provided in the links below:
Related Information
- Davis-Besse Reactor Vessel Head Degradation
- Steam Generator Action Plan
- Reactor Vessel Integrity
- View an Animated Image of a Pressurized Water Reactor
Page Last Reviewed/Updated Thursday, March 29, 2012