摘要
为了更好地对核电厂安全壳与主系统进行整体安全分析,选用一体化严重事故程序与系统程序RELAP5进行直接耦合。并采用了主系统压力边界的破口作为耦合界面和安注系统在主系统上的接口作为耦合界面这2种耦合方式。利用加压容器内的流体向安全壳堆坑喷放的算例Marviken CFT 24验证了这2种直接耦合方法的可行性和耦合程序进行整体安全分析的适用性。
The integral severe accident analysis code and RELAP5 were directly coupled for improving the overall safety analysis of the containment and primary system. Two kinds of coupling were implemented, i.e. breaks on the pressure boundary between the primary system and containment, interfaces between the safety injection systems and primary system. The feasibility of this coupling methodology and the applicability of the coupling code were verified through the calculation of a numerical case Marviken CFT 24 in which a pressurized vessel inflow to the containment reactor cavity.
作者
武小莉
李伟
邓坚
邓纯锐
张明
郭超
袁红胜
Wu Xiaoli;Li Wei;Deng Jian;Deng Chunrui;Zhang Ming;Guo Chao;Yuan Hongsheng(Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2018年第2期157-161,共5页
Nuclear Power Engineering
基金
国防科技工业核动力技术创新中心专项研究项目(HDLCXZX-2017-HD-012)
