Investigation of Heat Transfer for Fluid Flow through Porous Media: Application to a Pebble-Bed Reactor
In this paper, a new type of nuclear reactor, Pebble Bed Water-cooled Reactor (PBWR), is presented that consists of millions of Micro-Fuel Elements, and the TRISO-coated fuel particles(MFE) fill the fuel assembly disorderly and form a porous media structure with internal heat source. The present investigation aims at providing heat transport capability which can match with the heat generated by the core, so as to provide a set of thermal hydraulic parameters of the primary loop. So the key parameters including the pressure drop, void fraction, heat transfer coefficients and the profiles of temperature and DNBR are calculated for the equilibrium core in this paper. The calculation not only includes the liquid region, but the water-steam two phase region and the superheated steam region. The results show that the maximum fuel temperature is much lower than the design limitation and the flow distribution can meet the cooling requirement in the reactor core. The main design parameters that leave sufficient safety margin were also put forward in this paper.
Pebble-bed reactor porous media void fraction heat transfer pressure drop
Xiaoyu CAI Suizheng QIU Guanghui Su Wenxi Tian
State Key Laboratory of Multiphase Flow in Power Engineering, Xi’an Jiaotong University, Xi’an 710049, China；School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, Shaanxi 710049, P R China
国际会议
上海
英文
1624-1635
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）