Published October 2000 | Version v1
Miscellaneous

Development process of aging management programs for major SSCs of a PWR plant

  • 1. Korea Power Engineering Company, Yongin (Korea, Republic of)
  • 2. Korea Electric Power Research Institute, Taejon (Korea, Republic of)

Description

A feasibility study for the continued operation of Kori Unit 1, PLiM Phase I, showed more adequacy of continued operation beyond the design life. Recently, a Phase II study was initiated to provide several technical licensing documents by performing additional systematic evaluations on a wider range of components. The objective of this paper is to present the methodology and draft results from life assessment and aging management processes for the Korean PLiM study. In order to explain the program, the following three major topics are summarized for 3 components and 7 commodity groups; 1) technical guidelines to provide evaluation methodology and procedure, 2) key findings in the aging management process of the lead plant and, 3) lessons learned and the works to do. From a technical point of view, the preliminary results give the possibility as a prototypal application. However, at present, further efforts including additional analyses in relation to periodic safety review are being made to assure the safety and reliability of the lead plant beyond the design life

Part of:
Proceedings of the KNS autumn meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the KNS autumn meeting
Imprint Pagination
[CD-ROM]
Journal Page Range
[8 p.]

Conference

Title
2000 autumn meeting of the KNS
Dates
26-27 Oct 2000
Place
Taejon (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
34050684
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
AGING; DESIGN; FEASIBILITY STUDIES; KORI-1 REACTOR; LIFETIME; PWR TYPE REACTORS; SAFETY ANALYSIS
Descriptors DEC
ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
6 refs, 2 figs, 5 tabs