کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
5444702 1511108 2017 7 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Dimension of the forced vessel water level based on subcooling margin of core outlet coolant in CPR1000 nuclear power plants
کلمات کلیدی
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی انرژی (عمومی)
پیش نمایش صفحه اول مقاله
Dimension of the forced vessel water level based on subcooling margin of core outlet coolant in CPR1000 nuclear power plants
چکیده انگلیسی
The core cooling and monitoring system (CCMS) supplies the sub-cooling margin (ΔTSAT) and the pressure vessel water level (L VSL) information for State Oriented Procedure (SOP) to identify the core cooling state in post-accident conditions, as some special accidents such as the rupture of the vessel vent line will lead to both train A and train B L VSL measurements failure, the forced L VSL values have to be designed and set in the CCMS to ensure the correct diagnosis of primary system state in these scenarios. Considering the inherent relationship between ∆TSAT and L VSL from the point of view of thermal-hydraulics, the forced L VSL values are dimensioned based on ∆TSAT while taking into consideration the presence of non-condensable gases in primary system and the operating state of reactor coolant pumps. These values have been practically applied in CPR1000 nuclear power plants.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Energy Procedia - Volume 127, September 2017, Pages 103-109
نویسندگان
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