کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
5474836 | 1521085 | 2018 | 19 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Sensitivity analysis of VERA-CS and FRAPCON coupling in a multiphysics environment
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کلمات کلیدی
Consortium for Advanced Simulation of Light Water ReactorsHPCMPACTFRAPCONBEPUFOMLocaCOBRA-TFVERA-CSCASLMDNBREOCPWRRisk assessment - ارزیابی ریسکLoss of coolant accident - از دست دادن تصادف خنک کنندهBest estimate plus uncertainty - بهترین برآورد همراه با عدم قطعیتSensitivity analysis - تحلیل حساسیتOat - جو دو سرPressurized Water Reactor - راکتور آب تحت فشارProbability distribution function - عملکرد توزیع احتمالیFuel performance - عملکرد سوختLOTUS - لوتوسFigure of merit - معیار شایستگیEnd Of Cycle - پایان چرخهPdf - پی دی افUncertainty quantification - کمی سازی عدم قطعیتOne-at-a-time - یکی یکی
موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
مهندسی انرژی و فناوری های برق
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چکیده انگلیسی
A demonstration and description of the LOCA Toolkit for US light water reactors (LOTUS) is presented. Through LOTUS, the core simulator VERA-CS developed by CASL is coupled with the fuel performance code FRAPCON. The coupling is performed with consistent uncertainty propagation with all model inconsistencies being well-documented. Monte Carlo sampling is performed on a single 17Â ÃÂ 17 fuel assembly with a three cycle depletion case. Both uncertainty quantification (UQ) and sensitivity analysis (SA) are used at multiple states within the simulation to elucidate the behavior of minimum departure from nucleate boiling ratio (MDNBR), maximum fuel centerline temperature (MFCT), and gap conductance at peak power (GCPP). The SA metrics used are the Pearson correlation coefficient, Sobol sensitivity indices, and the density-based, delta moment independent measures. Results for MDNBR show consistency among all SA measures, as well for all states throughout the fuel lifecycle. MFCT results contain consistent rankings between SA measures, but show differences throughout the lifecycle. GCPP exhibits predominantly linear relations at low and high burnup, but highly nonlinear relations at intermediate burnup due to abrupt shifts between models. Such behavior is largely undetectable to traditional regression or variance-based methods and demonstrates the utility of density-based methods.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Annals of Nuclear Energy - Volume 111, January 2018, Pages 683-701
Journal: Annals of Nuclear Energy - Volume 111, January 2018, Pages 683-701
نویسندگان
Cole Blakely, Hongbin Zhang, Heng Ban,