The evaluation of intergranular stress corrosion cracking problems of stainless steel piping in Taiwan BWR-6 nuclear power plant
Description
Taiwan BWR-6 Kuosheng nuclear power plant unit 1 implemented the inspection of the intergranular stress corrosion cracking (IGSCC)-susceptible weldments of stainless steel piping in the reactor recirculation, reactor water clean-up, residual heat removal, core spray and feedwater systems. The purpose of this paper is to present the status of the fracture problems in the weldments. The crack growth analysis due to IGSCC and the standard weld overlay design based on the ASME Code Section XI and NUREG-0313 Rev. 2 for the fracture weldments are discussed in detail. Then, the contingent programs including the inspection program, fracture evaluation, and the standard weld overlay, are completely established to prevent pipe break during the reactor operation. (orig.)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 191
- Journal Issue
- 2
- Journal Page Range
- p. 245-254
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- 2. International workshop on the integrity of nuclear components
- Dates
- 20-21 Apr 1998
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Switzerland
- INIS RN
- 31002785
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CORROSION; CRACKS; FAILURES; FRACTURES; GRAIN BOUNDARIES; INSPECTION; MAINTENANCE; NUCLEAR POWER PLANTS; REACTOR SAFETY; STAINLESS STEELS; WELDING
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; FABRICATION; FAILURES; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; JOINING; MICROSTRUCTURE; NUCLEAR FACILITIES; POWER PLANTS; SAFETY; STEELS; THERMAL POWER PLANTS; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 7 refs.