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Article type: Research Article
Authors: Nemoto, Yoshiyukia; * | Keyakida, Satoshib | Uchimoto, Tetsuyac | Takaya, Shigerud | Tsukada, Takashia
Affiliations: [a] Nuclear Science and Engineering Directorate, Japan Atomic Energy Agency, 2-4 Shirane, Shirakata, Tokai-mura, Naka-gun, Ibaraki, Japan | [b] Sumitomo Metal Technology, Inc., Amagasaki, Japan | [c] Institute of Fluid Science, Tohoku University, Sendai, Japan | [d] Advanced Nuclear System Research and Development Directorate, Japan Atomic Energy Agency, Ibaraki, Japan
Correspondence: [*] Corresponding author: Yoshiyuki Nemoto, Nuclear Science and Engineering Directorate, Japan Atomic Energy Agency, 2-4 Shirane, Shirakata, Tokai-mura, Naka-gun, Ibaraki 311-1195, Japan. Tel.: +81 29 282 5349; Fax: +81 29 282 6122; E-mail: yoshiyuki.nemoto@oecd.org
Abstract: The authors previously reported that magnetic flux leakage data, measured using a flux gate (FG) sensor, showed a correlation with the irradiation-assisted stress corrosion cracking (IASCC) susceptibility of neutron-irradiated austenitic stainless alloys. This paper presents a study conducted to develop a diagnostic system that can detect IASCC precursors in stainless steels by measuring the magnetic properties of the material. The eddy current method and alternating current (AC) magnetization method were used, as these will be more practical for use in actual reactors. Probes were developed for these measurement methods, providing sufficient tolerance for environments in nuclear reactors. An attempt was also made to improve spatial resolution by manufacturing a smaller probe. A sensor system was designed for remote control, performance tests were conducted by measuring neutron-irradiated specimens and mock specimens, and magnetic data were evaluated by comparing the IASCC susceptibility of the specimens. It was proved that the sensor system developed in this study is capable of detecting IASCC precursors. Further developments necessary for application in actual nuclear reactors and the mechanism of correlation between magnetic properties and IASCC susceptibility were also discussed.
Keywords: Nuclear reactor, IASCC, austenitic stainless steel, prediction, irradiation
DOI: 10.3233/JAE-2011-1326
Journal: International Journal of Applied Electromagnetics and Mechanics, vol. 35, no. 2, pp. 123-139, 2011
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