原子能科学技术2016，Vol.50Issue(5)：829-834,6.DOI:10.7538/yzk.2016.50.05.0829
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
Research on PTS Transient Temperature Field of Key Position of RPV for Chashma Nuclear Power Plant
左巧林 1秋穗正 2王明军1
作者信息
- 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
- 折叠
摘要
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 .关键词
恰希玛核电厂/压力容器温度场/PTS瞬态Key words
Chashma NPP/temperature field of RPV/PTS transient分类
能源科技引用本文复制引用
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):829-834,6.
