核技术 ›› 2015, Vol. 38 ›› Issue (9): 90601-090601.doi: 10.11889/j.0253-3219.2015.hjs.38.090601

• 核能科学与工程 • 上一篇    下一篇

基于多孔介质模型的压水堆堆芯温场数值模拟

陈 森1 刘 余2 田茂林1 田文喜1 秋穗正1 苏光辉1   

  1. 1(西安交通大学 核科学与技术学院 西安 710049) 2(中国核动力研究设计院 核反应堆系统设计技术重点实验室 成都 610041)
  • 收稿日期:2014-07-29 修回日期:2015-01-14 出版日期:2015-09-10 发布日期:2015-09-10
  • 通讯作者: 田文喜,E-mail: wxtian@mail.xjtu.edu.cn E-mail:cs081515@163.com
  • 作者简介:陈森,男,1987年出生,2012年毕业于哈尔滨工程大学,现从事反应堆热工水力学研究
  • 基金资助:

    国家自然科学基金(No.11125522)资助

PWR core transient temperature numerical simulation based on porous media model

CHEN Sen1 LIU Yu2 TIAN Maolin1 TIAN Wenxi1 QIU Suizheng1 SU Guanghui1   

  1. 1(Institute of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China) 2(Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610041, China)
  • Received:2014-07-29 Revised:2015-01-14 Online:2015-09-10 Published:2015-09-10

摘要:

针对压水堆的复杂结构特点,对堆芯采用多孔介质模型,建立完整的压力容器堆芯模型,使用商用软件CFX对压力容器堆芯的热工水力特性进行数值模拟,得到偏环运行和典型事故工况下冷却剂的热工水力响应特性。计算结果表明:应用多孔介质模型能有效正确直观显示堆芯的冷却剂温度分布情况,在偏环运行工况下堆芯会出现偏心现象,而通过瞬态事故工况计算结果表明堆芯中上部冷却剂温度最高,对压水堆的热工安全具有一定指导作用。

关键词: 压水堆, 堆芯, 多孔介质模型, 瞬态工况

Abstract:

Background: The coolant flow and heat transfer in the reactor are significant to the safety of pressure water reactor (PWR). Purpose: This study aims to obtain the coolant flow and heat transfer characteristics in the reactor core. Methods: The complete model of pressure vessel is built by Pro/E, and the thermal hydraulic characteristics of the core are simulated with commercial software CFX by using the porous medium model in the core. Results: The simulation results show that the application of porous media model can display the core coolant temperature distribution effectively and correctly, and the asymmetric operation conditions can cause asymmetric on reactor core. The transient accident calculation results show that the highest temperature of the coolant appears in the upper of the core. Conclusion: The porous media model can be used in the reactor core and it has a certain reference value for the thermal-hydraulic safety of pressurized water reactor.

Key words: Pressurized water reactor, Reactor core, Porous media, Transient conditions