小破口失水事故非能动系统瞬态特性研究
Study on Coupling Characteristics of Small Break LOCA in Advanced PWR
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摘要: 为了解先进压水堆小破口失水事故下非能动安全壳冷却系统、非能动堆芯冷却系统、非能动余热排出系统的瞬态响应特性，需开展小破口失水事故下反应堆冷却剂系统和安全壳的耦合响应特性研究。分析结果表明，小破口失水事故下，耦合分析中非能动余热排出系统、非能动堆芯冷却系统、自动卸压系统和非能动安全壳冷却系统的特性与独立计算有较大差异，小破口失水事故下耦合分析得到的安全壳压力峰值小于独立计算。Abstract: In order to understand the transient response characteristics of the passive containment cooling system, the passive core cooling system and the passive residual heat removal system after the small break LOCA in an advanced pressurized water reactor, the coupling response characteristics of the reactor coolant system and the containment in SBLOCA are studied. The analysis results show that in the SBLOCA, the characteristics of the passive residual heat removal system, the passive core cooling system and the passive containment cooling system in the coupling analysis are quite different from the independent calculations. The containment peak pressure obtained by the coupling analysis in the SBLOCA is less than that by the independent calculation.
期刊类型引用(4)
1. Shuai Yang，Xiang?BinLi，Yu?ShengLiu，Jia?NingXu，De?ChenZhang. Response characteristics of PWR primary circuit under SBLOCAs considering steam bypass discharging. Nuclear Science and Techniques. 2024(06): 113-125 . 
必应学术2. 朱梦馨，殷松涛，王海军，王宁宁. 压水堆管道小破口蒸汽临界流泄漏实验研究. 核动力工程. 2023(02): 84-90 . 
本站查看3. 张盼，潘昕怿，王业辉，赵传奇. 核电厂中小LOCA事故下PSA成功准则研究. 核科学与工程. 2023(04): 898-905 . 百度学术4. 黄志刚，张妍，彭传新，昝元锋，卓文彬，闫晓. 小型堆稳压器波动管双端破口试验研究. 核动力工程. 2021(06): 82-86 . 本站查看其他类型引用(3)
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