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Dynamic simulation of the gas-cooled space nuclear reactor system using SIMCODE
Annals of Nuclear Energy ( IF 1.9 ) Pub Date : 2021-04-22 , DOI: 10.1016/j.anucene.2021.108293
Tao Meng , Kun Cheng , Fulong Zhao , Chenchao Xia , Sichao Tan

One dimensional space nuclear reactor system analysis code—SIMCODE is developed and five typical transient operation conditions are calculated, including the system startup, the loss of flow accident, the loss of heat sink accident, the reactivity insertion accident, and the small loss of coolant accident. These conditions are part of the key performance of the space nuclear reactor system and are related with both the individual characteristics of each component and the coupled characteristics between all the components. By analyzing the simulation results, system transient performance and coupled system characteristics are acquired. The information can provide helpful information for the system evaluation, safety system design, and emergency strategy setup. Based on the simulation, system control suggestions are also proposed and will be beneficial for further researches.



中文翻译:

使用SIMCODE对气冷空间核反应堆系统进行​​动态仿真

开发了一维空间核反应堆系统分析代码SIMCODE,并计算了五个典型的瞬态运行条件,包括系统启动,流失事故,散热片事故,反应性插入事故和冷却液损失小事故。这些条件是空间核反应堆系统关键性能的一部分,并且与每个组件的单独特性以及所有组件之间的耦合特性有关。通过分析仿真结果,获得了系统暂态性能和耦合的系统特性。该信息可以为系统评估,安全系统设计和应急策略设置提供有用的信息。根据模拟,

更新日期:2021-04-22
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