| 超临界水冷堆典型非失水事故模拟 |
| |
| 引用本文： | 曹臻,刘晓晶,杨珏,程旭.超临界水冷堆典型非失水事故模拟[J].原子能科学技术,2013,47(7):1162-1168. |
| |
| 作者姓名： | 曹臻 刘晓晶 杨珏 程旭 |
| |
| 作者单位： | 1.上海交通大学 核科学与工程学院，上海200240；2.中科华核电技术研究院有限公司，广东 深圳518026 |
| |
| 摘 要： | 基于修改后的最佳估算程序ATHLET-SC建立了典型的超临界水冷反应堆系统模型。对3种典型的非失水事故（失去给水加热、汽轮机失去负载且旁排未开启、给水泵卡轴）进行了模拟和敏感性分析，得到了堆功率、质量流量、最高包壳温度和最高燃料中心温度随时间变化的计算结果。结果表明，上述事故中系统压力、最高燃料包壳温度和最高燃料中心温度均可满足事故安全准则。
|
| 关 键 词： | 超临界水冷堆 ATHLET-SC程序 安全分析 |
Typical Non-LOCA Accident Analysis of Supercritical Water Cooled Reactor |
| |
| CAO Zhen,LIU Xiao-jing,YANG Jue,CHENG Xu.Typical Non-LOCA Accident Analysis of Supercritical Water Cooled Reactor[J].Atomic Energy Science and Technology,2013,47(7):1162-1168. |
| |
| Authors: | CAO Zhen LIU Xiao-jing YANG Jue CHENG Xu |
| |
| Affiliation: | 1.School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China; 2.China Nuclear Power Technology Research Institute, Shenzhen 518026, China |
| |
| Abstract: | Based on the revised best-estimate code AHTLET-SC, a typical supercritical water cooled reactor (SCWR) system was modeled. Three non-LOCA accidents (loss of feed water heating, loss of turbine load without turbine bypass and reactor coolant pump seizure) were chosen to perform accident simulation and sensitivity analysis. Some important results e.g. core power, mass flow rate, the highest cladding temperature, and the highest fuel pellet centerline temperature were obtained. The results indicate that all parameters satisfy the safety criteria in the accidents mentioned above. |
| |
| Keywords: | supercritical water cooled reactor ATHLET-SC code safety analysis |
| 本文献已被 CNKI 等数据库收录！ |
| 点击此处可从《原子能科学技术》浏览原始摘要信息 |
|
点击此处可从《原子能科学技术》下载全文 |
|
