原子能科学技术2012，Vol.46Issue(9)：1067-1073,7.
中国实验快堆一回路热工水力稳态计算程序开发
Development of Thermal-Hydraulic Steady-State Analysis Program for Primary Loop of China Experimental Fast Reactor
摘要
Abstract
According to the characteristics of structure and steady-state for primary loop of China Experimental Fast Reactor (CEFR), a thermal-hydraulic steady-state analysis program was developed by using Fortran language. This paper focused on the development of a set of subroutine of physical properties of sodium and the sodium flow and heat transfer correlations for different operation conditions. And the difference among these correlations was compared. The calculation program was developed based on the steady model. At last, the thermal-hydraulic characteristics of steady-state of the primary loop of CEFR at full power were calculated. The calculation results are consistent with the design parameters and the correctness of the developed subroutines and steady-state calculation program was proved.关键词
钠冷快堆/热工水力/稳态计算Key words
sodium cooled fast reactor/ thermal-hydraulic/ steady-state calculation分类
能源科技引用本文复制引用
饶彧先,崔满满,郭赟..中国实验快堆一回路热工水力稳态计算程序开发[J].原子能科学技术,2012,46(9):1067-1073,7.基金项目
教育部留学回国人员科研启动资金资助项目(20101174) （20101174）
