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Vol.3 No.4 previous AA 37 - 38 - NT 44 - 45

Academic Articles
Regular Paper Vol.4No.1 (2012) p.22 - p.35

Capability of Ultrasonic Testing for Cast Austenitic Stainless Steel in Japanese Pressurized Water Reactors

Kazunobu SAKAMOTO1,*Takashi FURUKAWA2,Ichiro KOMURA2, Youitsu YAGIHASHI2 and Tsuyoshi MIHARA3
1Japan Nuclear Energy Safety Organization, 4-1-28, Toranomon, Minato-ku, Tokyo, 105-0001, Japan
2Japan Power Engineering and Inspection Corporation, 14-1, Benten-cho, Tsurumi-ku, Yokohama, 230-0044, Japan
3University of Toyama, 3190 Gofuku, Toyama-shi, Toyama, 930-8555, Japan.
Flaw detection and sizing capabilities for cast austenitic stainless steel (CASS) which is widely used in primary loop of Japanese pressurized water reactors (PWR) are studied using conventional UT techniques currently applied on the CASS in in-service inspection program in Japan, Phased Array (PA) technique, as well as inspection by large size probe. The objective of the study was to make sure the accuracy of detection and sizing of inner surface flaws from the outside diameter piping surface by ultrasonic testing (UT) of which primary mode is longitudinal wave.
The result showed that currently available UT techniques are capable to detect the small cracks stable enough under postulated accident loads even after the thermal aging. With regard to the sizing capability, the result suggested that some consideration shall be taken into account when applying the technique if cracks were detected and technical breakthrough might be expected in the future.
Cast austenitic stainless steel, CASS, Pressurized Water Reactor, PWR, Ultrasonic testing, UT
Full Paper: PDF EJAM Vol.4No.1 pp22.-35 "Capability of Ultrasonic Testing for Cast Austenitic Stainless Steel in Japanese Pressurized Water Reactorss
Article Information
Article history:
Received 26 Dec 2011
Accepted 22 May 2012