Technical safety issues related to residual life assessment of major LWR (light water reactor) components and structures

Conference · Thu Jan 01 00:00:00 EST 1987

OSTI ID:5447264

Shah, V N; MacDonald, P E; Burns, Jr, J J

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.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA); Nuclear Regulatory Commission, Rockville, MD (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5447264
• Report Number(s): EGG-M-21787; CONF-8710289-1; ON: DE88006770
• Resource Relation: Conference: Water reactor safety information meeting, Washington, DC, USA, 26 Oct 1987; Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
AGING
CONTAINMENT BUILDINGS
PRESSURE VESSELS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
PWR TYPE REACTORS
CONTAINMENT
CONTROL ELEMENTS
EMBRITTLEMENT
IRRADIATION
PIPES
PRESSURIZERS
PUMPS
RADIATION EFFECTS
REACTOR SAFETY
SERVICE LIFE
STEAM GENERATORS
THERMAL FATIGUE
BOILERS
BUILDINGS
CONTAINERS
COOLING SYSTEMS
ENERGY SYSTEMS
FATIGUE
MECHANICAL PROPERTIES
REACTORS
SAFETY
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled