Published April 2007
| Version v1
Journal article
Validation of ultrasonic testing for PWR pressurizer dissimilar metal weld
Creators
- 1. Central Research Inst. of Electric Power Industry, Materials Science Research Laboratory, Yokosuka, Kanagawa (Japan)
Description
Validation of ultrasonic testing (UT) for detecting stress corrosion cracks (SCCs) in the Pressurizer's dissimilar metal weld of nuclear power plant, PWR, was carried out. Appropriate UT methods using probes consist of separate transmit and receive piezo-electric elements with longitudinal wave can detect both axial and circumferential SCCs ranged from 12% to 23% thickness of weld. (author)
Additional details
Publishing Information
- Journal Title
- Hozengaku
- Journal Volume
- 6
- Journal Issue
- 1
- Journal Page Range
- p. 21-27
- ISSN
- 1348-7795
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 43115415
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CRACKS; INCONEL 600; PRESSURIZERS; PROBES; PWR TYPE REACTORS; SIZE; STRESS CORROSION; ULTRASONIC TESTING; VALIDATION; WELDED JOINTS
- Descriptors DEC
- ACOUSTIC TESTING; ALLOY-NI76CR15FE8; ALLOYS; ALUMINIUM ADDITIONS; ALUMINIUM ALLOYS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CORROSION; CORROSION RESISTANT ALLOYS; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; INCONEL ALLOYS; IRON ALLOYS; JOINTS; MATERIALS; MATERIALS TESTING; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIMONIC; NONDESTRUCTIVE TESTING; POWER REACTORS; REACTORS; TESTING; THERMAL REACTORS; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs., 11 figs., 5 tabs.