Abstract
As field experiences of material degradation has been increasing in reactor internals of nuclear power plants, Thermal and Nuclear Power Engineering Society has started development of inspection and evaluation guidelines for reactor internals to maintain their structural integrity and required function. The guidelines reasonably determine inspection coverage, test methods, inspection period and evaluation criteria from the view point of reactor safety. The present paper reports a basic concept of the guidelines and examples of inspection and evaluation methods for pressurized water reactor (PWR) baffle former bolt.
