کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
5475058 | 1521087 | 2017 | 13 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Evaluation of an IVR-ERVC strategy for a high power reactor using MELCOR 2.1
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کلمات کلیدی
DCHECCMMP1Lumped parameter methodExternal reactor vessel coolingERVCMAAPIVR-ERVCMCCIMP2RCPIVRRCSPRALPMLocaSBODVIFCIDOEChFMolten pool - استخر سربHeat transfer - انتقال گرماStation black out - ایستگاه بیرون آمدنICI - اینجاProbabilistic risk analysis - تجزیه و تحلیل ریسک احتمالیTransient analysis - تجزیه و تحلیل گذراCore degradation - تخریب هستهSafety injection - تزریق ایمنیdirect vessel injection - تزریق مستقیم قطرهLoss-of-Coolant Accident - حوادث ناشی از خنک کنندهIn-vessel retention - درگیری در داخل رگCFD - دینامیک سیالاتComputational fluid dynamics - دینامیک سیالات محاسباتیReactor coolant system - سیستم خنک کننده راکتورCritical heat flux - شار حرارتی بحرانیStainless steel - فولاد ضد زنگMELCOR - ملکورCRP - پروتئین واکنشی سی یا سی. آر. پی Reactor coolant pump - پمپ خنک کننده راکتور
موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
چکیده انگلیسی
The IVR-ERVC (In-Vessel Retention of molten corium through External Reactor Vessel Cooling) is an effective severe accident management strategy for reducing the possibility of a reactor containment failure by terminating the severe accident progress inside a reactor. However, the technical applicability and feasibility of the IVR-ERVC design for an advanced high-power reactor should still be validated considering the uncertainties of physical models, the initial conditions and assessment methodologies. In this paper, the severe accident progress of the APR1400 for a large break loss-of-coolant accident is analyzed using MELCOR 2.1 when the reactor cavity is fully flooded. The chronology of events, the thermal hydraulic behaviors and the core degradation behaviors are analyzed. As a result of the MELCOR calculation, a relatively large portion of particulate debris is relocated to the bottom of the lower head at the end of the debris-quench mode, preventing effective heat transfer to the ex-vessel wall. Because the lower head wall cannot be ablated by melting in the MELCOR, the in-vessel wall temperature is increased as compared to the melting point of the lower head. The heat flux is maximized at approximately 3.5e4Â s and it is compared to the results from the lumped parameter method.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Annals of Nuclear Energy - Volume 109, November 2017, Pages 337-349
Journal: Annals of Nuclear Energy - Volume 109, November 2017, Pages 337-349
نویسندگان
Kukhee Lim, Yongjin Cho, Seokwon Whang, Hyun Sun Park,