Comparative study between single core model and detail core model of CFD modelling on reactor core cooling behaviour

International Nuclear Science, Technology and Engineering Conference 2017

原子能学

Darmawan, R.^1

Malaysian Nuclear Agency, Bangi Selangor Kajang

4300, Malaysia^1

关键词: Comparative studies;    Continuous development;    Experimental methods;    Fukushima dai-ichi nuclear power plants;    Investigation and analysis;    Nuclear power plant safeties;    Nuclear power program;    Nuclear-power industry;   

Others  :  https://iopscience.iop.org/article/10.1088/1757-899X/298/1/012030/pdf
DOI  :  10.1088/1757-899X/298/1/012030

来源: IOP

【 摘 要 】

Nuclear power industry is facing uncertainties since the occurrence of the unfortunate accident at Fukushima Daiichi Nuclear Power Plant. The issue of nuclear power plant safety becomes the major hindrance in the planning of nuclear power program for new build countries. Thus, the understanding of the behaviour of reactor system is very important to ensure the continuous development and improvement on reactor safety. Throughout the development of nuclear reactor technology, investigation and analysis on reactor safety have gone through several phases. In the early days, analytical and experimental methods were employed. For the last four decades 1D system level codes were widely used. The continuous development of nuclear reactor technology has brought about more complex system and processes of nuclear reactor operation. More detailed dimensional simulation codes are needed to assess these new reactors. Recently, 2D and 3D system level codes such as CFD are being explored. This paper discusses a comparative study on two different approaches of CFD modelling on reactor core cooling behaviour.