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Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core
المؤلفون المشاركون
Xiang, Yan
Tian, Wenxi
Ye, Linrong
Wang, Mingjun
Wang, Xin’an
Deng, Jian
Su, G. H.
Qiu, Suizheng
المصدر
Science and Technology of Nuclear Installations
العدد
المجلد 2020، العدد 2020 (31 ديسمبر/كانون الأول 2020)، ص ص. 1-12، 12ص.
الناشر
Hindawi Publishing Corporation
تاريخ النشر
2020-08-28
دولة النشر
مصر
عدد الصفحات
12
الملخص EN
The thermal hydraulic and neutronics coupling analysis is an important part of the high-fidelity simulation for nuclear reactor core.
In this paper, a thermal hydraulic and neutronics coupling method was proposed for the plate type fuel reactor core based on the Fluent and Monte Carlo code.
The coupling interface module was developed using the User Defined Function (UDF) in Fluent.
The three-dimensional thermal hydraulic model and reactor core physics model were established using Fluent and Monte Carlo code for a typical plate type fuel assembly, respectively.
Then, the thermal hydraulic and neutronics coupling analysis was performed using the developed coupling code.
The simulation results with coupling and noncoupling analysis methods were compared to demonstrate the feasibility of coupling code, and it shows that the accuracy of the proposed coupling method is higher than that of the traditional method.
Finally, the fuel assembly blockage accident was studied based on the coupling code.
Under the inlet 30% blocked conditions, the maximum coolant temperature would increase around 20°C, while the maximum fuel temperature rises about 30°C.
The developed coupling method provides an effective way for the plate type fuel reactor core high-fidelity analysis.
نمط استشهاد جمعية علماء النفس الأمريكية (APA)
Ye, Linrong& Wang, Mingjun& Wang, Xin’an& Deng, Jian& Xiang, Yan& Tian, Wenxi…[et al.]. 2020. Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core. Science and Technology of Nuclear Installations،Vol. 2020, no. 2020, pp.1-12.
https://search.emarefa.net/detail/BIM-1209425
نمط استشهاد الجمعية الأمريكية للغات الحديثة (MLA)
Ye, Linrong…[et al.]. Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core. Science and Technology of Nuclear Installations No. 2020 (2020), pp.1-12.
https://search.emarefa.net/detail/BIM-1209425
نمط استشهاد الجمعية الطبية الأمريكية (AMA)
Ye, Linrong& Wang, Mingjun& Wang, Xin’an& Deng, Jian& Xiang, Yan& Tian, Wenxi…[et al.]. Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core. Science and Technology of Nuclear Installations. 2020. Vol. 2020, no. 2020, pp.1-12.
https://search.emarefa.net/detail/BIM-1209425
نوع البيانات
مقالات
لغة النص
الإنجليزية
الملاحظات
Includes bibliographical references
رقم السجل
BIM-1209425
قاعدة معامل التأثير والاستشهادات المرجعية العربي "ارسيف Arcif"
أضخم قاعدة بيانات عربية للاستشهادات المرجعية للمجلات العلمية المحكمة الصادرة في العالم العربي
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