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海洋条件反应堆热工水力系统分析程序开发及验证

程坤 谭思超 陈莹莹 孟涛 文静

哈尔滨工程大学学报2017,Vol.38Issue(8):1223-1230,8.
哈尔滨工程大学学报2017,Vol.38Issue(8):1223-1230,8.DOI:10.11990/jheu.201605093

海洋条件反应堆热工水力系统分析程序开发及验证

Development and validation of nuclear reactor thermal-hydraulic system analysis code under ocean conditions

程坤 1谭思超 1陈莹莹 2孟涛 1文静3

作者信息

  • 1. 哈尔滨工程大学 核安全与仿真技术国防重点学科实验室,黑龙江 哈尔滨 150001
  • 2. 环境保护部核与辐射安全中心,北京 100088
  • 3. 中国核动力研究设计院 第一研究所,四川 成都 610041
  • 折叠

摘要

Abstract

A nuclear reactor thermal-hydraulic system analysis code for ocean conditions is lacking in the development process of floating nuclear power plants in China.To solve this problem, inertial acceleration models of a coolant under ocean conditions were established based on the mathematical description of typical ship movement.A thermal-hydraulic system analysis code suitable for marine nuclear plants was developed by adding an ocean condition calculation module to a commercial system analysis program.Experimental validation and comparison with different codes were performed to evaluate the validity of ocean condition modeling and program modification.Result shows that the developed code can effectively simulate the flow fluctuation experiment under rolling condition, and the calculation results under different motion conditions are in good agreement with those of RETRAN-02/GRAV and other codes of the same type, thereby verifying the reliability of the code calculation results under motion conditions.

关键词

惯性加速度模型/系统分析程序/程序验证/海洋条件/热工水力/安全分析/浮动核电站

Key words

inertial acceleration model/system analysis code/code validation/ocean condition/thermal hydraulic/safety analysis/floating nuclear power plant

分类

能源科技

引用本文复制引用

程坤,谭思超,陈莹莹,孟涛,文静..海洋条件反应堆热工水力系统分析程序开发及验证[J].哈尔滨工程大学学报,2017,38(8):1223-1230,8.

基金项目

黑龙江省青年学术骨干支持计划(1254G017) (1254G017)

中央高校基本科研业务费专项资金项目(HEUCFD1512). (HEUCFD1512)

哈尔滨工程大学学报

OA北大核心CSCDCSTPCD

1006-7043

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