Residual life assessment of major pressurized water reactor components

This paper presents an assessment of the aging (time-dependent degradation) of selected major pressurized water reactor components and structures. The main criterion used in selecting these components is their role in preventing the release of fission products to the public. The stressors, possible degradation sites and mechanisms, potential failure modes, and currently used methods for nondestructive examination are discussed for five major light water reactor components: pressure vessels, containment structures, reactor coolant piping, steam generators, and reactor pressure vessel supports. Important technical issues related to life extension of these components are identified, and several recommendations are provided.