志賀原子力発電所 1 号機 高周波誘導加熱による配管応力改善工事について
英字タイトル:
Induction Heating Stress Improvement for pipe of primary loop recirculation system at Shika Nuclear Power Station Unit 1
著者:
倉田 勝 Masaru KURATA 森本 英光 Hidemitsu MORIMOTO 座主 正貴 Masaki ZASU 根上 司 Tsukasa NEGAMI
発刊日:
公開日:
Induction Heating Stress ImprovementShika Nuclear Power Station
Induction Heating Stress Improvement for pipe of primary loop recirculation system at Shika Nuclear Power Station Unit 1
著者:
倉田 勝 Masaru KURATA 森本 英光 Hidemitsu MORIMOTO 座主 正貴 Masaki ZASU 根上 司 Tsukasa NEGAMI
発刊日:
公開日:
カテゴリ: 第11回
キーワードタグ:Induction Heating Stress ImprovementShika Nuclear Power Station
概要
Significant numbers of intergranular stress corrosion cracking incidents have occurred in welded austenitic stainless steel of primary loop recirculati on system piping in boiling water reactors. This crack was also occurred in Shika Nuclear Power unit 1. This time, stress improvement processing by hig frequency guidance overheating has been performed as preventive maintenance to the weld line with which we are anxious about generating of stress corr ion cracking among the weld lines of primary loop recirculation system piping. The principle, a procedure, and a result are introduced in this paper.
