原子能科学技术2013，Vol.47Issue(7)：1162-1168,7.DOI:10.7538/yzk.2013.47.07.1162
超临界水冷堆典型非失水事故模拟
Typical Non-LOCA Accident Analysis of Supercritical Water Cooled Reactor
曹臻 1刘晓晶 1杨珏 2程旭1
作者信息
- 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
- 折叠
摘要
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.关键词
超临界水冷堆/ATHLET-SC程序/安全分析Key words
supercritical water cooled reactor/ ATHLET-SC code/ safety analysis分类
能源科技引用本文复制引用
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):1162-1168,7.
