1987•OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)Requires access
Technical safety issues related to residual life assessment of major LWR (light water reactor) components and structures
V.N. Shah, P.E. MacDonald, J.J. Burns
Open publisher page 0 citations
Abstract
This paper presents an assessment of the time-dependent degradation or aging of selected major light water reactor components and structures. The stressors, possible degradation sites and mechanisms are identified for several major LWR components: pressurized water reactor (PWR) reactor pressure vessels, PWR containment structures, PWR coolant piping and safe ends, PWR surge and spray lines, PWR steam generators, PWR pressurizers, PWR reactor coolant pumps, PWR control rod drive mechanisms, PWR reactor internals, LWR reactor pressure vessel supports, Boiling Water Reactor (BWR) containments, BWR reactor pressure vessels, and BWR recirculation piping. The technical safety issues related to aging and license renewal of these components are also discussed. The general concept of residual life assessment procedures for the major components is presented. 14 refs., 1 fig., 2 tabs.