炉内構造物検査用の渦電流探傷技術の開発
英字タイトル:
Development of Eddy Current Technique for Components in Reactor Pressure Vessel
著者:
西水 亮 Akira NISHIMIZU 松井 哲也 Tetsuya MATSUI 小池 正浩 Masahiro KOIKE 吉田 功 Isao YOSHIDA 野中 善夫 Yoshio NONAKA
発刊日:
公開日:
Components in RPVEddy Current TestingFlaw Length SizingFlexible Probe
Development of Eddy Current Technique for Components in Reactor Pressure Vessel
著者:
西水 亮 Akira NISHIMIZU 松井 哲也 Tetsuya MATSUI 小池 正浩 Masahiro KOIKE 吉田 功 Isao YOSHIDA 野中 善夫 Yoshio NONAKA
発刊日:
公開日:
カテゴリ: 第3回
キーワードタグ:Components in RPVEddy Current TestingFlaw Length SizingFlexible Probe
概要
1 flexible multi-coil eddy current testing (ECT) probe and a method for measuring the length of flaws have meen developed for inspecting comple x structures in the reactor pressure vessel of nuclear plants. The probe can be applied to curved surfaces that are larger than a curvature rad ius of 20 mm. And we propose the nethod for measuring the flaw length by introducing a decibel drop method of the ECT output signal. From the te st results of various EDM notches using the probe and the measuring method, we found that the ccuracy of the length sizing was within +/- 3 mm.
