کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
6759464 1431394 2018 12 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Development of safety analysis code for SCWR and its LOCA analysis of CSR1000
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
Development of safety analysis code for SCWR and its LOCA analysis of CSR1000
چکیده انگلیسی
At last, the Loss of Coolant Accidents (LOCAs) with a small break size and a large break size occurring at the main coolant line of Chinese Super-Critical Water-cooled Reactor (CSR1000) are simulated. The results show that CSR1000 with its official safety system design can be cooled down during the considered accidents and code TACOS has good feasibility for safety analysis of supercritical water systems.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Engineering and Design - Volume 327, February 2018, Pages 100-111
نویسندگان
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