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Residual life assessment of major light water reactor components: Overview: Volume 1

R. L. Cloud, Jeff Cook, Daye, W.G. Hopkins, L.J. House, Vasdev Malhotra, H. Mantle, W.R. Mikesell, G.R. Odette, Robert O. Ritchie

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Abstract

This report presents an assessment of the aging (time-dependent degradation) of selected major light water reactor components and structures. The stressors, possible degradation sites and mechanisms, potential failure modes and currently used nondestructive examinations, in-service inspection (ISI) and life assessment methods are discussed for seven major light water reactor components: pressurized water reactor (PWR) and boiling water reactor (BWR) pressure vessels, PWR containment structures, PWR reactor coolant piping, PWR steam generators, BWR recirculation piping, and reactor pressure vessel supports. Unresolved technical issues related to life extension of these components, including requirements for advanced ISI and life assessment methods, are also discussed.

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Available abstract

Key concepts: Light-water reactor, Boiling water reactor, Piping, Pressurized water reactor, Nuclear engineering, Coolant, Reactor pressure vessel, Containment (computer programming)