Uncertainty analysis in the neutronic parameters generation for BWR and PWR coupled thermal-hydraulic–neutronic simulations
عنوان مقاله: Uncertainty analysis in the neutronic parameters generation for BWR and PWR coupled thermal-hydraulic–neutronic simulations
شناسه ملی مقاله: SENACONF01_249
منتشر شده در اولین کنگره سراسری فناوریهای نوین ایران با هدف دستیابی به توسعه پایدار در سال 1393
شناسه ملی مقاله: SENACONF01_249
منتشر شده در اولین کنگره سراسری فناوریهای نوین ایران با هدف دستیابی به توسعه پایدار در سال 1393
مشخصات نویسندگان مقاله:
Seyed Mahdi Mostashiri - University of Amirkabir Industrial, Tehran, Iran
Ali Haghighi Shad - University of Amirkabir Industrial, Tehran, Iran
Heidar Abbasi - heidar.abbasi@yahoo.com
Narges Ghasempoor - Hakim Sabzevari University, Applicable physic - elementary particle physic, Iran
خلاصه مقاله:
Seyed Mahdi Mostashiri - University of Amirkabir Industrial, Tehran, Iran
Ali Haghighi Shad - University of Amirkabir Industrial, Tehran, Iran
Heidar Abbasi - heidar.abbasi@yahoo.com
Narges Ghasempoor - Hakim Sabzevari University, Applicable physic - elementary particle physic, Iran
The Best Estimate analysis consists of a coupled thermal-hydraulic and neutronic description of the nuclear system’s behavior; uncertainties from both aspects should be included and jointly propagated. This paper presents a study of the influence of the uncertainty in the macroscopic neutronic information that describes a three-dimensional core model on the most relevant results of the simulation of a Reactivity Induced Accident (RIA). The analyses of a BWR-RIA and a PWR-RIA have been carried out with a three-dimensional thermalhydraulic and neutronic model for the coupled system TRACE-PARCS and RELAP-PARCS.
کلمات کلیدی: Uncertainty analysis, Neutronic parameters, BWR, PWR
صفحه اختصاصی مقاله و دریافت فایل کامل: https://civilica.com/doc/345169/