کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
11019777 1717620 2019 7 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Analysis of the configurations and heat transfer of corium pool in RPV lower plenum
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
Analysis of the configurations and heat transfer of corium pool in RPV lower plenum
چکیده انگلیسی
The corium containing stainless steel, partially oxidized zirconium cladding and fuel materials in the lower plenum may separate into immiscible liquids at high temperatures that influence the heat flux into vessel during in-vessel melt retention (IVR). In this work, the stratification of the corium in the lower plenum and the distribution of heat flux on the outside of vessel for AP1000 were assessed by three well-accepted 3-layer models developed by Esmaili & Khatib-Rahbar (model 1), Seiler (model 2), Salay & Fichot (model 3) respectively. In addition, the heat transfer in the corium is analyzed for a typical 1000 MWe Advanced PWR in China after a hypothetical station blackout accident. The results shown that the maximum heat flux of corium pool obtained by model 1 and 2 are both smaller than the CHF of AP600. Although it is slightly larger in model 2, enough safety margin is still retained compared with the CHF of AP1000.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Annals of Nuclear Energy - Volume 124, February 2019, Pages 172-178
نویسندگان
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