大飯発電所における原子炉容器出口管台予防保全対策工事の実施について


英字タイトル:
INLAY Method Using the Cylindrical Container for Reactor Vessel Outlet Nozzle of PWRfor Ohi Nuclear Power Station
著者:
市木 成樹 Shigeki ICHIKI 岩橋 裕樹 Hiroki IWAHASHI 寺田 典夫 Norio TERADA 中村 康夫 Yasuo NAKAMURA 山本 和秀 Kazuhide YAMAMOTO
発刊日:
公開日:
カテゴリ: 第7回
キーワードタグ:

概要

Preventive maintenance techniques against PWSCC found in Alloy 600 welds have been applied progressively, however, in February 2008, a defect of PWSCC had been found in an outlet nozzle to safe-end weld of Reactor vessel of PWR in Ohi Nuclear Power Station Unit 3 during an outage. Then the defect was removed and after its safety was confirmed, the unit was placed in operation. In the next outage, INLAY method using the cylindrical container was applied an d repair welding for the removed part was performed. In addition, circumferential grooving to remove Alloy 600 of the inner surface of the outlet nozzle and circumferential welding with PWSCC resistant Alloy 690 were applied. This circumferential grooving and welding techniques were also applied for all outlet nozzles of Ohi Unit 4 as a preventive maintenance.


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