Published 2004 | Version v1
Miscellaneous

Stress corrosion crack growth evaluation in primary loop of nuclear power plant

  • 1. Korea Electric Power Research Institute, Taejon (Korea, Republic of)
  • 2. KOPEC, Yongin (Korea, Republic of)
  • 3. Korea Hydro and Nuclear Power Co., Ltd., Seoul (Korea, Republic of)

Description

The most important mode of subcritical crack growth is primary water stress corrosion crack, which was the reported mechanism from the root cause analysis of the crack in the bimetallic welds. Stress corrosion crack growth evaluations was carried out for several flaw shapes of both axial and circumferential flaws, using the steady-state stresses including residual stresses. This evaluation considered the possibility of additional flaws in the primary loops of nuclear power plant, even though no such flaws have been identified by ultrasonic test. Consequently, results show that the predicted flaw sizes will determine acceptability for continued service and maintenance

Part of:
Proceedings of the KSME 2004 spring annual meeting

Additional details

Publishing Information

Publisher
KSME
Imprint Place
Seoul (Korea, Republic of)
Imprint Title
Proceedings of the KSME 2004 spring annual meeting
Imprint Pagination
[CD-ROM]
Journal Page Range
[4 p.]

Conference

Title
2004 spring annual meeting of the KSME
Dates
28-30 Apr 2004
Place
Pyeongchang (Korea, Republic of)

Optional Information

Notes
6 refs, 4 figs, 1 tab