摘要
导出了反应堆时空动力学方程的近似解析解。此解的中子密度空间分布曲率是随堆功率变化的,因此它比点堆模型方程的解析解精确。可用于反应堆现场运行所需的监督性快速计算。对反应堆的安全运行有重要的指导意义。
An approximate analytic solution of reactor space-time dynamic equation is derived. The space curvature of neutron density of this solution is changed according to the changes of reactor power, so it is more precise than the analytic solution of point reactor model. By means of this solution, a rapid supervisory calculation can be performed at the reactor running scene, and it has directive meaning for the reactor running safety.
出处
《核科学与工程》
CSCD
北大核心
2006年第4期313-315,共3页
Nuclear Science and Engineering
基金
国家自然科学基金资助项目(105751131)
