压水堆一回路系统热工水力稳态计算模型的建立  

Models Development for Thermal-hydraulic Steady-state Calculation of the Primary Loop of Reactor

作　　者：段孟强[1] 陈五星[1] 季晨龙[1] 

机构地区：[1]海军驻431厂军事代表室,辽宁葫芦岛125004

出　　处：《四川兵工学报》2013年第12期132-134,137,共4页Journal of Sichuan Ordnance

摘　　要：为对压水堆一回路系统热工参数的选择,堆芯安全分析等工作提供帮助,针对压水堆一回路系统的特点,建立了压水堆一回路系统热工水力稳态计算模型;模型包括棒状燃料元件平均通道及热通道、立式U型管自然循环蒸汽发生器及一回路流体强迫循环流量等热工水力计算模型,并使用fortran语言编制计算程序,将某型压水堆结构参数作为输入参数进行计算并对该型压水堆堆芯热通道在不同堆芯寿期下的热工参数进行计算;计算结果表明:一回路系统热工参数计算值同设计值吻合良好,证明了模型建立的合理性;不同堆芯寿期下的热通道热工参数均低于设计限值,满足安全需要。In order to provide help for the choice of thermal-hydraulic parameter of the primary loop system and the analysis of safety of the core, a model was built for thermal-hydraulic steady-state calculation of the primary loop of marine reactor according to the characteristic of marine reactor. A model for calculation of average and hot channel of the rod fuel element, a model for calculation of thermal-hydraulic characteristic of U-tube steam generator and a model for calculation of flow of the primary loop fluid were involved. A program was developed according to the models. The structure parameters of a marine reactor were input and the thermal-hydraulic parameters of this marine reactor under different reactor core life time were got. The calculated results show that the calculation results of thermal-hydraulic parameters of the primary loop system are consistent with the design parameters and the thermal-hydraulic parameters of hot channel under different reactor core life time are under the design limit parameters.

关 键 词：压水堆 热工水力 稳态计算 

分 类 号：TL333[核科学技术—核技术及应用]