Published May 2002 | Version v1
Miscellaneous

Fatigue evaluation of PHTS pumps for a domestic CANDU nuclear power plant

  • 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

Part of:
Proceedings of the KNS-KARP Joint spring meeting

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