一体化核动力装置的热工水力特性模型及计算  

Thermohydraulic Characteristics of Integrated Nuclear Power Plant

作　　者：苏光辉[1] 郭玉君[1] 解衡[1] 贾斗南[1] 周涛[1] 

机构地区：[1]西安交通大学,西安710049

出　　处：《西安交通大学学报》2000年第1期33-36,共4页Journal of Xi'an Jiaotong University

基　　金：核工业基金!J94EY7082

摘　　要：介绍了一体化核动力装置的特点；建立了一套完整的数学物理模型，包括堆芯模型、基本的热工水力模型、传热学模型、计算方法模型、物性模型及辅助模型等；分析了一体化核动力装置的热工水力特性，根据模型编制了程序，经过实堆计算及ＲＥＴＲＡＮ０２ 验证，证明程序是正确、实用的；最后给出了程序的算例．An advanced model of nuclear power plant is developed with the characteristics of small volume, light weight, simplified structure, enhanced natural circulation and small probability of large break LOCA. A program using the FORTRAN77 language is developed; it makes use of many models including those for thermohydraulics, heat transfer, properties of fluid and solid and the core. Auxiliary models are also considered. These models are tested using RETRAN02 and the data obtained from actual operation of nuclear reactor. The program has the module structure in addition to being used friendly and it can be executed on a microcomputer. Calculated results are presented to validate the model.

关 键 词：一体化 核动力装置 热工水力模型 反应堆 

分 类 号：TL33[核科学技术—核技术及应用]