基于SCWR堆芯结构的子通道程序开发与应用  

Development and Application of Sub-channel Analysis Code Based on SCWR Core

作　　者：傅晟威[1] 许志红[2] 杨燕华[2] 

机构地区：[1]海军工程大学核能科学与工程系,湖北武汉430000 [2]上海交通大学核科学与工程学院,上海200240

出　　处：《原子能科学技术》2011年第3期345-350,共6页Atomic Energy Science and Technology

基　　金：国家"973"计划资助项目(2007CB209804);国家自然科学基金资助项目(50776058)

摘　　要：为能够对超临界水堆(SCWR)堆芯进行子通道分析,开发了新的子通道分析程序SABER。该程序在COBRA程序的基础上改进了网格结构和热传导模型,加入了新的边界条件和水物性模块,以适用于SCWR慢谱燃料组件的子通道分析。为评估程序的适用性,采用该程序对SCWR堆芯概念设计中的慢谱燃料组件进行子通道建模,并进行稳态计算。结果表明,该程序能够用于SCWR堆芯的子通道计算分析,并较好地解决了慢谱组件计算中慢化通道和冷却通道间的热耦合及逆向流动的模拟问题。The sub-channel analysis code SABER was developed for thermal-hydraulic analysis of supercritical water-cooled reactor（SCWR） fuel assembly.The extended computational cell structure,a new boundary conditions,3 dimensional heat conduction model and water properties package were implemented in SABER code,which could be used to simulate the thermal fuel assembly of SCWR.To evaluate the applicability of the code,a steady state calculation of the fuel assembly was performed.The results indicate good applicability of the SABER code to simulate the counter-current flow and the heat exchange between coolant and moderator channels.

关 键 词：超临界水堆 慢谱燃料组件 子通道分析 SABER程序 

分 类 号：TL331[核科学技术—核技术及应用]