کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
10293425 | 511843 | 2005 | 10 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Assessment study of the coupled code RELAP5/PARCS against the Peach Bottom BWR turbine trip test
دانلود مقاله + سفارش ترجمه
دانلود مقاله ISI انگلیسی
رایگان برای ایرانیان
کلمات کلیدی
Three-dimensionalTSVBWROECDNPPNEAbpV - bpvVVER - vvereNuclear Energy Agency - آژانس انرژی هسته ایIAEA - آژانس بین المللی انرژی اتمیinternational atomic energy agency - آژانس بین المللی انرژی اتمیBest estimate - بهترین تخمینPVM - تاریخBoiling water reactor - رآکتور آب جوشOrganization for Economic Co-operation and Development - سازمان همکاری و توسعه اقتصادیCross-section - سطح مقطعParallel virtual machine - موازی ماشین مجازیnuclear power plant - نیروگاه هستهایEuropean Commission - کمیسیون اروپایی
موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
چکیده انگلیسی
The modeling of complex transients in nuclear power plants (NPP) remains a challenging topic for best estimate three-dimensional coupled code computational tools. This technique is, nowadays, extensively used for simulating transients that involve core spatial asymmetric phenomena and strong feedback effects between core neutronics and reactor loop thermal-hydraulics. In this framework, the Peach Bottom BWR turbine trip experiment 2 is considered. The test involves a rapid positive reactivity addition into the core generated by a water hammer load. To perform a numerical simulation of such phenomenon a reference case was calculated using the coupled code RELAP5/PARCS. An overall data comparison shows good agreement between calculated and measured pressure wave trend in the core region. However, the predicted power response during the excursion phase did not match correctly the experimental tendency. For this purpose, a series of sensitivity analyses have been carried out to identify the most probable reasons of such discrepancy. It was found out that the uncertainties related to the cross-sections modeling and to the thermal-hydraulic closure relationships are the main source of the incorrect power feedback response during the transient.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Engineering and Design - Volume 235, Issue 16, July 2005, Pages 1727-1736
Journal: Nuclear Engineering and Design - Volume 235, Issue 16, July 2005, Pages 1727-1736
نویسندگان
Anis Bousbia Salah, Giorgio M. Galassi, Francesco D'Auria, BoÅ¡tjan KonÄar,