Published 2005 | Version v1
Miscellaneous

Development of Heat Exchanger Thermal Performance Monitoring Program

  • 1. Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

Description

Through researches for the last three years, as a part of KNICS R and D program, we were able to identify current status and problems of thermal performance test, analysis, and diagnosis being performed in nuclear power plants, Korea. In the old nuclear power plants, performance analysis procedures of not only turbine cycle but safety-related heat exchanger in the primary system were being required. In particular, in the case of the Gori units 3,4 where periodic safety assessment(PSR) was performed recently, safety-related heat exchanger management program was required as follow-up measures of PSR. Performance analysis of safety-related heat exchangers is used to evaluate reliability of heat exchangers during long-term operation. The significance of this analysis lies in the fact that it can evaluate safety and viability at the same time. However, there exists discrepancy between conditions of normal operation and design, which makes it difficult to develop performance analysis procedure. This study focused on development of performance analysis procedure of safety-related heat exchangers in primary system

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

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

Conference

Title
2005 spring meeting of the KNS
Dates
26-27 May 2005
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
37041992
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
HEAT EXCHANGERS; KORI-3 REACTOR; MONITORING; NUCLEAR POWER PLANTS; PERFORMANCE; RELIABILITY; SAFETY
Descriptors DEC
ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
1 ref, 1 fig