Published 2007 | Version v1
Miscellaneous

A Theoretical Method to Predict Wear of Plugged Tubes of Steam Generators

  • 1. Sunchon National Univ., Sunchon (Korea, Republic of)
  • 2. Chonbuk National Univ., Jeonju (Korea, Republic of)
  • 3. Korea Electric Power Research Inst., Daejeon (Korea, Republic of)

Description

Wear of steam generator tubes has been focused on in nuclear power industries for a long time. In case a certain amount of a steam generator tube wall is revealed to be worn out, which is usually caused by flow induced vibrations, by nondestructive tests, the tube is required to be plugged to avoid leakage of primary water into the secondary side and possible serious sequences. Recently, the question about the integrity of plugged tubes has been issued. This is because the tube might experience the wear even after the plugging, therefore, in a worst situation the plugged tube could be ruptured and then give mechanical impacts on neighboring tubes. If this scenario happens the plugged tube should have been stabilized by an appropriate method. In order to decide whether the stabilizer is necessary for the plugged tube, we need to evaluate the wear of the tube after the plugging. This paper proposes a theoretical and practical method to predict wear of plugged tubes, which is based on actual measurement data from some PWR plants in service

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

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

Conference

Title
2007 spring meeting of the KNS
Dates
10-11 May 2007
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
38113453
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
LEAKS; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; STEAM GENERATORS; TUBES; WEAR
Descriptors DEC
BOILERS; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
4 refs, 6 figs