先进核电厂大LOCA事故下安全壳参数敏感性分析
Sensitivity Analysis of Containment Parameters Under Large LOCA Accidents in Advanced Nuclear Power Plant
冷段作为冷却剂从蒸汽发生器出来到反应堆压力容器的主管道部分，是一回路重要的组成部分。应用PAREO程序，对华龙一号安全壳压力响应进行敏感性分析。定量评价了自由容积、热构件件面积、喷淋流量、内部大气温度，对失水事故工况下的安全壳压力和温度的影响。研究结果表明：热构件面积对安全壳压力响应过程最为敏感。该研究结果可为安全壳设计、安全分析和安全评审提供技术支持。
old leg is an important part of primary coolant circuit, as main pipe for coolant coming out from vapor generator to RPV. Use PAREO program to run containment response sensitivity analysis for Hualong One. Quantitatively evaluate the impact of free volume, thermal component dimension, spray flow and internal atmosphere temperature on pressure and temperature of containment under LOCA. Results show that, thermal component dimension is the most sensitive factor to containment response. This result can be used for supporting the safety design, safety analysis and safety assess of containment.
孙燕宇、周蓝宇、周涛
反应堆、核电厂安全科学原子能技术基础理论
压水堆失水事故（LOCA）热构件面积压力
PWR LOCA Thermal component dimension Pressure
孙燕宇,周蓝宇,周涛.先进核电厂大LOCA事故下安全壳参数敏感性分析[EB/OL].(2021-11-15)[2025-08-19].http://www.paper.edu.cn/releasepaper/content/202111-34.点此复制
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