沸騰水型原子力プラントにおける低炭素ステンレス鋼の応力腐食割れについて(<特集>原子力エネルギーの安全利用技術)

概要

論文の詳細を見る
L-grade stainless steels as 316NG, SUS316L and SUS304L have been used for the BWR reactor internals and re-circulation pipes as SCC resistant materials. However, SCC of the L-grade material components were reported recently in many Japanese BWR plants. The detail investigation of the components showed the fabrication process such as welding, machining and surface finishing strongly affected SCC occurrence. In this paper, research results of SCC of L-grade stainless steels, metallurgical investigation of core shrouds and re-circulation pipings, and features of SCC morphology were introduced. Besides, the structural integrity of components with SCC, countermeasures for SCC and future R&D planning were introduced.
一般社団法人日本エネルギー学会の論文
2004-07-20