Published 1991 | Version v1
Journal article

Life cycle considerations for pressurized water reactor vessels

  • 1. Grove Engineering, Inc., Rockville, MD (United States)

Description

This paper reports on the pressurized water reactor (PWR) reactor vessel identified by the Surry 1 life extension project as a critical element for life extension considerations. This ranking was based on a prioritization of all the plant systems, components, and structures taking into account difficulty to repair/replace and wear out considerations. The study also determined the vessel has a high probability for extended service life based on best estimate analysis of actual usage, maintenance, in-service inspection programs, and presently available methods for prolonging vessel life. Feasibility studies have also been performed for PWR reactor pressure vessels designed by the three domestic vendors. All of these studies concluded that the reactor vessel has a high probability for extended service life beyond the original license period

Additional details

Publishing Information

Journal Title
Proceedings of the American Power Conference
Journal Volume
53
Series
Proc. Am. Power Conf.
Journal Page Range
184-185
ISSN
0097-2126
CODEN
PAPWA

Conference

Title
53. annual American power conference.
Dates
29 Apr - 1 May 1991.
Place
Chicago, IL (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
23015036
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FEASIBILITY STUDIES; IN-SERVICE INSPECTION; LIFETIME; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR VESSELS
Descriptors DEC
CONTAINERS; ENRICHED URANIUM REACTORS; INSPECTION; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-9104106--.