Heat transfer from a 2 x 2 wire-wrapped rod bundle to supercritical pressure water

作     者：Wang, Han Bi, Qincheng Leung, Laurence K. H. 

作者机构：North China Elect Power Univ Sch Nucl Sci & Engn Beijing 102206 Peoples R China Xi An Jiao Tong Univ State Key Lab Multiphase Flow Power Engn Xian 710049 Peoples R China Canadian Nucl Labs Chalk River ON K0J 1J0 Canada 

出 版 物：《INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER》 (国际传热与传质杂志)

年 卷 期：2016年第97卷第0期

页      面：486-501页

核心收录：

学科分类：080702[工学-热能工程] 08[工学] 0807[工学-动力工程及工程热物理] 0802[工学-机械工程] 0801[工学-力学（可授工学、理学学位）] 

基　　金：Atomic Energy of Canada Limited Fundamental Research Funds for the Central Universities [2015QN08] 

主　　题：Supercritical water Heat transfer 2 x 2 rod bundle Wire-wrapped spacer Empirical correlation 

摘      要：An experiment has been completed to study the heat transfer characteristics of supercritical water in a 2 x 2 wire-wrapped rod bundle. The rod-bundle simulated a fuel assembly with four heated rods and was installed inside a square channel with rounded corners. A wire of 1.2 mm outer diameter was helically wrapped around the outer surface of each heated rod at an axial pitch of 200 mm. The experimental parameters covered the pressure of 23-28 MPa, mass flux of 400-1000 kg/m(2)s and heat flux range on the rod surface of 200-1000 kW/m(2). Wall temperatures obtained at each heated rod were examined and average heat transfer coefficients were calculated at each measuring location of the rod and compared against those obtained with a 2 x 2 bare rod bundle. Heat transfer characteristics of supercritical water in the 2 x 2 rod bundle were analyzed with respect to the variations of heat flux, mass flux and pressure. Eleven heat transfer correlations were assessed against the current set of test data. The results showed that the correlations of Jackson and Krasnoshchekov-Protopopov give the best predictions on average Nusselt number. (C) 2016 Elsevier Ltd. All rights reserved.