Development of Sub-channel Analysis Code for Super Critical CANDU Type Reactor
The paper presents the development of a sub-channel thermal hydraulic analysis code named SUBCHAN. The code was originally developed to analyze super critical CANDU type reactor which has such characters as horizontally fuel channels, hevay water moderated, super critical light water cooled, any type of fuel bundle with or without thorium rods. Thermal- hydraulic model of SUBCHAN is based on four partial differential equations that describe the conservation of mass, energy and momentum vector in axial and lateral directions for the water liquid/vapor mixture. The heat transfer correlations and pressure drop correlations used in the SUBCHAN code are presented in this paper. The water properties pacakge of the code is based on the Industrial Formulation 1997 for the Thermodynamic Properties of Water and Steam. The heat transfer correlation of super critical region is based on the experimental investigation of Xian Jiaotong University and Dyadyakin and Popov correlation. By calculating the TACR case, which is operating at 12.5MPa pressure, compared with the results of ASSERT-PV code, the paper gets the conclusion that the development of the SUBCHAN code with super critical water property package is successful. Then the paper uses the SUBCHAN code to analyze CANDU-SCWR which is operating at 25.0MPa pressure. The paper get the conclusion that the SUBCHAN code can be used to analyze sub- channel thermal hydraulic analysis of CANDU-SCWR fuel channel.
Sub-channel SCWR CANDU ASSERT-PV
YU Jiyang WANG Songtao JIA Baoshan
Department of Engineering Physics, Tsinghua University 100084, Beijing
国际会议
上海
英文
150-160
2007-03-12（万方平台首次上网日期，不代表论文的发表时间）