Fatigue evaluation of PHTS pumps for a domestic CANDU nuclear power plant
Creators
- 1. KOPEC, Taejon (Korea, Republic of)
- 2. KEPRI, Taejon (Korea, Republic of)
Description
Fatigue evaluation on primary heat transport system pumps (33122) for a domestic CANDU nuclear power plant ware carried out as a part of a Plant Lifetime Management (PLIM) study. A methodology used in performing the evaluations was based on the NUREG-1800 and the evaluating were carried out for the pressure boundary regions based on the number of design and operating transients with consideration of environmental effects. The cumulative usage factors(CUFs) of PHTS pumps were identified high in order of Stuffing Box's Cooling Hole, Cutwater Region, Outlet Region, and etc. The stuffing box's cooling hole among these regions was evaluated that the fatigue usage factor for 50 years operation based on the design transients exceeded 1.0. But, the reevaluated cumulative usage factor based on the operating experience was below allowable limit. From the results of fatigue evaluations for the PHTS pumps, it is concluded that the fatigue will not be a significant safety issue even considering additionary 20 years continued operation
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS-KARP Joint spring meeting
- Imprint Pagination
- [CD-ROM]
- Journal Page Range
- [7 p.]
Conference
- Title
- 2002 joint spring meeting of the KNS-KARP
- Dates
- 23-24 May 2002
- Place
- Gwangju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 34009935
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CANDU TYPE REACTORS; DESIGN; FATIGUE; LIFETIME; PUMPS; SERVICE LIFE; TRANSIENTS
- Descriptors DEC
- EQUIPMENT; HEAVY WATER MODERATED REACTORS; LIFETIME; MECHANICAL PROPERTIES; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 10 refs, 1 fig, 7 tabs