原子能科学技术2011，Vol.45Issue(5)：541-547,7.
AP1000冷管段小破口失水事故分析
Analysis of Cold Leg Small Break LOCA for AP1000
杨江 1田文喜 1苏光辉 1秋穗正2
作者信息
- 1. 西安交通大学,动力工程多相流国家重点实验室,陕西,西安,710049
- 2. 西安交通大学,核科学与技术学院,陕西,西安,710049
- 折叠
摘要
Abstract
Based on the PWR best-estimate program RELAP5/MOD3. 4, the reactor coolant system and the passive core cooling system of AP1000 were modeled and analyzed. Some key transient parameters were obtained, including RCS pressure, break discharge, cladding temperature, etc. The result is in close agreement with the result generated by NOTRUMP code from Westinghouse (USA). The calculation results show that safeguard system of AP1000 can effectively lower the temperature and reduce the pressure of the first loop, also can prevent core overheating. The safety of AP1000 during a small-break loss-of-coolant accident is verified.关键词
AP1000/RELAP5/小破口失水事故Key words
AP1000/ RELAP5/ small-break loss-of-coolant accident分类
能源科技引用本文复制引用
杨江,田文喜,苏光辉,秋穗正..AP1000冷管段小破口失水事故分析[J].原子能科学技术,2011,45(5):541-547,7.
