摘要
以秦山Ⅰ期核电厂为参考,通过增加一系列工程性约束条件,对已有稳压器优化设计方案进行了改进。在秦山Ⅰ期一回路系统中,利用改进后的稳压器设计方案替代原设计方案,通过已建立的RELAP5计算模型,研究了在小破口给水丧失事故和给水丧失未能紧急停堆的预期瞬变下的系统响应特性,并与参考母型的计算结果进行了比较。研究结果表明:采用改进后的稳压器优化设计方案,提高了蒸汽发生器二次侧压力,有利于保障汽轮机效率和安全。本文研究范围内,在小破口给水丧失事故和给水丧失未能紧急停堆的预期瞬变中,优化模型与母型应对能力相当。
The pressurizer optimization scheme built by considering engineering con- straints was modified. Based on Qinshan I Nuclear Power Plant primary loop in which the original pressurizer design scheme was replaced by the modified one, a RELAP5 model was built and the performants of optimized pressurizer during SBLOCA-LOFW and LOFW-ATWS accidents were studied, and the results were compared with that of the original model. The results show that modified optimization scheme has yielded pressure increase in the secondary side of steam generator, which is in favor of ensuring steam turbine efficiency and safety. In the scope of this study, the capability of the opti- mization model coping with accidents is comparable with that of the original one.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2013年第12期2277-2282,共6页
Atomic Energy Science and Technology
