Development of sub-channel analysis code for CANDU-SCWR

摘要

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 horizontal fuel channels, heavy 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 package 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 Xi'an Jiaotong University and Dyadyakin and Popov correlation. By calculating the TACR case, which is operating at 12.5 MPa 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 25.0 MPa pressure. The paper gets the conclusion that the SUBCHAN code can be used to analyze the steady state sub-channel thermal-hydraulic analysis of CANDU-SCWR fuel channel.