کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
6762103 | 511725 | 2014 | 13 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Modeling RIA benchmark cases with FRAPTRAN and SCANAIR: A comparative exercise
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کلمات کلیدی
EDFÉlectricité de FranceCIEMATInstitut de Radioprotection et de Sûréte NucléaireIRSNPCMIReactivity insertion accidentPWRPNNLCSNTPNRIAOECDNEAFGRHTCNRCEOLCeA - CEAPacific Northwest National Laboratory - آزمایشگاه ملی شمال غربی اقیانوس آرامNuclear Energy Agency - آژانس انرژی هسته ایFission Gas Release - انتشار گازهای شکافتPressurized Water Reactor - راکتور آب تحت فشارFinite element model - روش اجزاء محدود یا روش المان محدود Organization for Economic Cooperation and Development - سازمان همکاری های اقتصادی و توسعهHeat transfer coefficient - ضریب انتقال حرارتPPN - مالیات بر ارزش افزودهsed - وend of life - پایان عمرFEM - پنجStrain energy density - چگالی انرژی فشارNuclear Regulatory Commission - کمیسیون تنظیم مقررات هسته ای
موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
مهندسی انرژی و فناوری های برق
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چکیده انگلیسی
The need for defining new RIA safety criteria has demonstrated the importance of performing a rigorous assessment of the transient codes capabilities. The present work is a comparative exercise devoted to identify the origin of the key deviations found between the predictions of FRAPTRAN-1.4 and SCANAIR-7.1 codes. To do so, the results of the calculations submitted by CIEMAT to the OECD/NEA RIA benchmark (CIP0-1, CIP3-1, VA-1 and VA-3 experiments) have been exploited. The advantage of these simulations is that the initial rodlet characterization, the transient power and the user assumptions were defined similarly in the two codes, which is essential to perform a consistent comparison. The comparative assessment has led to relevant insights about the codes performances. As for differences reported in the CIP0-1 clad temperatures, the heat transfer modeling across the oxide layer has been found to be mainly responsible. Likewise, the estimation of the gap closure time is directly related to the systematically higher clad hoop deformations predicted by FRAPTRAN-1.4. The differences between FRAPTRAN-1.4 and SCANAIR-7.1 fission gas release predictions reflect the different strategies adopted by the codes to model the complex processes involved in gas release during the transient.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Engineering and Design - Volume 278, 15 October 2014, Pages 150-162
Journal: Nuclear Engineering and Design - Volume 278, 15 October 2014, Pages 150-162
نویسندگان
I.C. Sagrado, L.E. Herranz,