کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
6758704 1431386 2018 12 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Ultimate pressure capacity of nuclear reactor containment buildings under unaged and aged conditions
ترجمه فارسی عنوان
ظرفیت فشار نهایی ساختمان های ضد انفجار هسته ای تحت شرایط نامناسب و سالم
کلمات کلیدی
ساختمان مهارکننده راکتور، ظرفیت فشار نهایی، تنزل، خوردگی یاب
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
چکیده انگلیسی
Using ABAQUS, a non-linear finite element analysis (FEA) was performed to evaluate and compare the effects of degradation mechanisms by aging on the ultimate pressure capacity (UPC) of APR1400 reactor containment building (RCB). As the primary degradation mechanisms, prestress loss, concrete aging, rebar corrosion, and liner corrosion were simulated in the modelling and calculations. The results for unaged reactor containment buildings showed that the failure sequence by the internal pressure build-up consisted of 4 stages and reinforcement yielding strain of reinforced concrete would be the most important factor governing the UPC of RCBs. Among the four degradation mechanisms, corrosion occurring on the outer and inner rebar layers was identified as the main degradation mechanism affecting most significantly the ultimate pressure capacity of the APR1400 reactor containment building.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Engineering and Design - Volume 335, 15 August 2018, Pages 128-139
نویسندگان
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