Development of the advanced phased array UT technique for accurate sizing of cracks in the nozzle welding
Creators
- 1. Mitsubishi Heavy Industries, Ltd., Kobe Shipyard and Machinery Works, Kobe, Hyogo (Japan)
- 2. Mitsubishi Heavy Industries, Ltd., Tokyo (Japan)
- 3. Kansai Electric Power Co., Inc., Osaka (Japan)
Description
Recently, preventive maintenance tasks for welding of safe-end nozzles of reactor vessels and steam generators of PWRs in Japan had been carried out sequentially. Before the maintenance tasks, inspection services were carried out and several crack indications were found by eddy current testing (ECT). These indications were found in the welding which made by 600 series nickel base alloy and evaluated as stress corrosion cracks which were oriented to the axial direction of the nozzle. Then investigations to evaluate the depth of cracks were carried out by ultrasonic testing (UT) from inner surface of the nozzles. However they were difficult to evaluate the depth of cracks due to the high attenuation of the ultrasonic propagation caused by large grain structure of welding. And also it was required high resolution near surface region for accurate sizing. Therefore development of advanced phased array UT techniques specialized for the sizing at this portion was carried out. This paper reports the development status and verification test results. Firstly simulations of the ultrasonic propagation in the welding were carried out to optimize beam profiles of phased array probes. Next prototype probes were manufactured and verification tests were conducted to evaluate the accuracy of depth sizing. It is shown that the developed techniques have high sizing accuracy for artificial stress corrosion cracks in the welding. (author)
Additional details
Additional titles
- Original title (Japanese)
- Nippon hozen gakkai dai-7-kai gakujutsu koenkai yoshishu
Publishing Information
- Imprint Title
- Proceedings of the 7th annual meeting of Japan Society of Maintenology
- Imprint Pagination
- 623 p.
- Journal Page Range
- p. 67-70
Conference
- Title
- 7. annual meeting of Japan Society of Maintenology
- Dates
- 13-15 Jul 2010
- Place
- Omaezaki, Shizuoka (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 44034010
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CRACKS; DEPTH; INCONEL 600; INSPECTION; NOZZLES; NUCLEAR POWER PLANTS; PROBES; PWR TYPE REACTORS; REACTOR MAINTENANCE; REACTOR VESSELS; SIZE; STEAM GENERATORS; STRESS CORROSION; ULTRASONIC TESTING; WELDED JOINTS
- Descriptors DEC
- ACOUSTIC TESTING; ALLOY-NI76CR15FE8; ALLOYS; ALUMINIUM ADDITIONS; ALUMINIUM ALLOYS; BOILERS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CONTAINERS; CORROSION; CORROSION RESISTANT ALLOYS; DIMENSIONS; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; INCONEL ALLOYS; IRON ALLOYS; JOINTS; MAINTENANCE; MATERIALS; MATERIALS TESTING; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIMONIC; NONDESTRUCTIVE TESTING; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; TESTING; THERMAL POWER PLANTS; THERMAL REACTORS; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 refs., 8 figs., 2 tabs. Imprint:Nippon hozen gakkai dai-7-kai gakujutsu koenkai yoshishu