کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
1566773 999825 2011 4 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Prediction of irradiation embrittlement of vanadium alloyed low nickel steel for future reactors
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی انرژی هسته ای و مهندسی
پیش نمایش صفحه اول مقاله
Prediction of irradiation embrittlement of vanadium alloyed low nickel steel for future reactors
چکیده انگلیسی

A comparison between pearlitic 2CrMoV steel (WWER-440) and 9% Cr based ferritic–martensitic steels (EUROFER 97 and LA12TaLC) is presented as regards irradiation induced ductile–brittle transition temperature shifts. For neutron doses of 1.5–2 dpa and irradiation temperatures around 300 °C the transition temperature shifts for WWER-440 steel and EUROFER 97 welds are comparable. In the temperature range 350–500 °C the radiation embrittlement levels of both steels are low. Moreover, post-irradiation annealing is proposed as a promising method to predict results of high temperature irradiation embrittlement from existing lower temperature irradiation embrittlement data.


► 2CrMoV and 9% Cr steels show comparable irradiation induced DBTT shifts at 300 °C.
► Radiation embrittlement of both steels is low at 350–500 °C.
► Annealing is method to predict results of high temperature irradiation embrittlement.
► Studies are required to qualify 2CrMoV steel for GEN IV applications.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Journal of Nuclear Materials - Volume 416, Issue 3, 30 September 2011, Pages 327–330
نویسندگان
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