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
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