کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
1566280 1514219 2012 14 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Behavior of stainless steels in pressurized water reactor primary circuits
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی انرژی هسته ای و مهندسی
پیش نمایش صفحه اول مقاله
Behavior of stainless steels in pressurized water reactor primary circuits
چکیده انگلیسی
A strong susceptibility for SCC of heavily cold worked austenitic stainless steels is evidenced in hydrogenated primary water typical of PWRs. It is shown that for a given cold-working procedure, SCC susceptibility of austenitic stainless steels materials increases with increasing cold-work. Results have shown also strong influences of the cold work on the oxide layer composition and of the maximum stress on the time to fracture.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Journal of Nuclear Materials - Volume 427, Issues 1–3, August 2012, Pages 364-377
نویسندگان
, , ,