کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
6758876 | 1431389 | 2018 | 16 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Application of regression, variance, and density based global sensitivity methods to integrated VERA-CS and BISON simulations
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کلمات کلیدی
MCNPConsortium for Advanced Simulation of Light Water ReactorsMPACTBEPUMonte Carlo N-particleCOBRA-TFReactivity insertion accidentORNLVERA-CSMDNBRPWRCASLINLHPCRIAFOMLocacIPS - CIPSOak Ridge National Laboratory - آزمایشگاه ملی Oak RidgeIdaho National Laboratory - آزمایشگاه ملی آیداهوRisk assessment - ارزیابی ریسکLoss of coolant accident - از دست دادن تصادف خنک کنندهBest estimate plus uncertainty - بهترین برآورد همراه با عدم قطعیتBison - بیسونSensitivity analysis - تحلیل حساسیتPressurized Water Reactor - راکتور آب تحت فشارNodal expansion method - روش گسترش متداولProbability distribution function - عملکرد توزیع احتمالیLOTUS - لوتوسFigure of merit - معیار شایستگیNEM - نهPdf - پی دی افUncertainty quantification - کمی سازی عدم قطعیتMoose - گوزن شمالی
موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
مهندسی انرژی و فناوری های برق
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چکیده انگلیسی
Uncertainty quantification (UQ) and sensitivity analyses (SA) are performed for coupled simulations between VERA-CS, a coupled pin resolved neutron transport and subchannel thermal hydraulics code, and the fuel performance code BISON. The interface between VERA-CS and BISON is performed in a multiphysics environment known as the LOCA Toolkit for U.S. light water reactors (LOTUS) currently under development at Idaho National Laboratory (INL). A focus is placed on using a variety of SA measures, including two regression based (Pearson and Spearman), one variance based (Sobol indices), and three moment independent measures (Delta moment independent measures with L1, L2, and Lâ norms). The problem under inspection is a single assembly depletion case for three fuel cycles. The figures of merit are the minimum departure from nucleate boiling ratio (MDNBR), maximum fuel centerline temperature (MFCT), and gap conductance at peak power (GCPP). SA results show MDNBR to be linear with consistent rankings throughout the fuel cycles. MFCT is linear, but with a change in rankings at the switch from open gap to closed gap models. GCPP is nonlinear at intermediate states that coincide with the onset of contact between fuel and cladding. These nonlinear states allow for the showcasing of higher order SA measures over first order methods.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Engineering and Design - Volume 332, June 2018, Pages 186-201
Journal: Nuclear Engineering and Design - Volume 332, June 2018, Pages 186-201
نویسندگان
Cole Blakely, Hongbin Zhang, Charlie Folsom, Heng Ban, Ronaldo Szilard,