کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
8085010 1521751 2016 8 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Neutronics and sub-channel thermal-hydraulics analysis of the Iranian VVER-1000 fuel bundle
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
Neutronics and sub-channel thermal-hydraulics analysis of the Iranian VVER-1000 fuel bundle
چکیده انگلیسی
In the present research, sub-channel thermal-hydraulic analysis of the Bushehr Nuclear Power Plant (BNPP) core, a Russian VVER-1000 type, at hot full power (HFP) and steady state BOC conditions is presented herein using modified COBRA-EN code. Required power distribution and hot channel factors were computed by our past neutronics calculations using MCNP-5 code. Due to increasing temperature, modification on the continuous-energy cross sections in the MCNP libraries are carried out using NJOY code. Maximum and average fuel temperature, enthalpy, void fraction, coolant temperature and density, coolant mass flow rate and pressure drop are calculated using different models. Thermal-hydraulics calculations of the most rated channel (hottest sub-channel), which is determined based on coupled neutronics-thermal hydraulics calculations are investigated and results in temperature, enthalpy, critical heat flux and MDNBR of the hottest sub-channel are found. Finally, our results are compared with analytical approaches and the reactor FSAR.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Progress in Nuclear Energy - Volume 87, March 2016, Pages 39-46
نویسندگان
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