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恰希玛核电厂压力容器各关键部位在PTS瞬态下的温度场研究
引用本文:左巧林,秋穗正,王明军.恰希玛核电厂压力容器各关键部位在PTS瞬态下的温度场研究[J].原子能科学技术,2016,50(5):829-835.
作者姓名:左巧林  秋穗正  王明军
作者单位:1.西安交通大学 核科学与技术学院,陕西 西安710049;2.上海核工程研究设计院,上海200233
摘    要:承压热冲击现象在核电厂延寿评估中应被重点关注。本文针对恰希玛核电厂1号机组的压力容器及堆内构件建立了完整的CFD模型,计算了正常工况下压力容器内冷却剂的速度场和温度场分布,计算结果与试验结果符合良好。本文详细研究了蒸汽发生器传热管破裂事故工况下压力容器接管及下降段中冷却剂的热工水力特性,并将计算结果与RELAP5计算结果进行对比,结果表明二者符合良好。本文研究可为反应堆压力容器老化管理评估的计算分析工作提供重要参考。

关 键 词:恰希玛核电厂    压力容器温度场    PTS瞬态

Research on PTS Transient Temperature Field of Key Position of RPV for Chashma Nuclear Power Plant
ZUO Qiao-lin,QIU Sui-zheng,WANG Ming-jun.Research on PTS Transient Temperature Field of Key Position of RPV for Chashma Nuclear Power Plant[J].Atomic Energy Science and Technology,2016,50(5):829-835.
Authors:ZUO Qiao-lin  QIU Sui-zheng  WANG Ming-jun
Affiliation:1.School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China 2.Shanghai Nuclear Engineering Research & Design Institute, Shanghai 200233, China
Abstract:The pressurized thermal shock (PTS) in the assessment of life extension of a nuclear power plant should be paid much attention to .For Chashma NPP No .1 unit ,a complete CFD model for RPV and its internals was established .Coolant velocity and temperature fields in RPV were simulated during normal state ,and the results are con-sistent with experimental data . The coolant thermal-hydraulic characteristics in the RPV nozzle and the downcomer under SGTR transient were also studied in detail .The results were compared with the calculation results by RELAP5 code , and the good agreement is achieved between them .The present research could be useful for the calcu-lation and analysis in RPV aging management evaluation .
Keywords:Chashma NPP  temperature field of RPV  PTS transient
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