首页|基于空间核反应堆事故工况下的仿真研究

基于空间核反应堆事故工况下的仿真研究

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随着我国航天事业的发展,空间核反应堆电源因其功率密度大、寿命长、环境适应性强、工作性能稳定等特点,已成为未来空间探索的理想动力能源。为了研究空间核反应堆在正常运行工况和掉落事故工况下的安全性,基于中子输运计算程序OpenMC对空间核反应堆开展临界仿真研究,得到正常工况下堆芯反应性、控制鼓价值以及燃耗计算等一系列重要参数。同时模拟分析了空间核反应堆在水淹和沙埋 2 种事故工况下的堆芯反应性和中子能谱。结果表明,空间核反应堆在保持控制鼓功能正常的掉落事故工况下仍然有3000pcm左右的负反应性以防止反应堆达到临界状态,保证了空间核反应堆在此事故工况下的安全性,表明此堆芯的设计是安全可靠的。空间核反应堆仿真研究对我国未来空间核反应堆实际应用具有一定的指导意义。计算结果为空间核反应堆的安全分析和事故分析提供了重要的参考数据。
Simulation Research under Accident Condition of Space Nuclear Reactor
With the development of China's aerospace industry,space nuclear reactor power supply has become an ideal power source for future space exploration due to its high power density,long life,strong environmental adaptabili-ty and stable working performance.In order to study the safety of space nuclear reactor under normal operating condi-tions and falling accident conditions,this paper conducted critical simulation research on space nuclear reactor based on neutron transport calculation program OpenMC,and obtaind a series of important parameters such as reactor core reactivity,control drum value and fuel depletion calculation under normal operating conditions.At the same time,the core reactivity and neutron energy spectrum of the space nuclear reactor under two accident conditions of flooding and sand burial were simulated and analyzed.The results show that the space nuclear reactor still has about 3000pcm neg-ative reactivity to prevent the reactor to reach the critical state under the normal drop accident condition of the control drum function,which ensures the safety of the space nuclear reactor under this accident condition,and indicates that the core design is safe and reliable.The simulation research of space nuclear reactor has certain guiding significance for the practical application of space nuclear reactor in China in the future.The calculation results in this paper pro-vide important reference data for the safety analysis and accident analysis of space nuclear reactors.

Space nuclear reactorNeutron transport calculation programAccident conditionSimulation calcula-tion

秦凯文、郝鹏飞、杨波、刘义保

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东华理工大学核科学与工程学院,江西 南昌 330013

东华理工大学核资源与环境国家重点实验室,江西 南昌 330013

空间核反应堆 中子输运计算程序 事故工况 仿真计算

国家自然科学基金江西省教育厅科技计划重点项目

11965001GJJ170428

2024

计算机仿真
中国航天科工集团公司第十七研究所

计算机仿真

CSTPCD
影响因子:0.518
ISSN:1006-9348
年,卷(期):2024.41(1)
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