1) point reactor neutron kinetics
点堆中子动力学
1.
A new numerical method of solving the point reactor neutron kinetics equations by using the technique of first order Taylor polynomials for the approximation of neutron density in integral of one step is presented.
使用中子密度一阶泰劳多项式分段近似技术，给出一个新的求解点堆中子动力学方程组的数值方法并采用全隐格式以克服方程组的刚性，同时确保解的必要精度。
2.
The improved Gear method-IGear for solving the point reactor neutron kinetics equations is presented.
求解点堆中子动力学方程的改进的Gear方法——IGear,以其高阶和大稳定域的性质保持了Gear方法适应性强,计算精度较高的优点,并改进了它的缺点。
3.
A numerical method solving the point reactor neutron kinetics equation by using the technique of second-order Taylor polynomials for the approximation of the neutron density in integral of one step was presented and optimized.
在求解点堆中子动力学方程组中,对中子密度使用分段全隐式高阶泰勒多项式近似技术,给出一求解点堆中子动力学方程组的数值积分方法,并对该方法进行了修正优化。
2) Neutron Kinetics
中子动力学
1.
Study on Coupling of Three-Dimension Space Time Neutron Kinetics Model and RELAP5 and Improvement of RELAP5;
RELAP5程序与三维时空中子动力学模型的耦合以及改进研究
2.
Development of spatio-temporal neutron kinetics simulation software for marine nuclear reactor core;
船用反应堆堆芯时空中子动力学仿真软件的研制
3.
According to the separation-of-variables method,an approximate analytic solution of the space-time neutron kinetics equation is derived for the homegeneous cylindrate reactor.
利用分离变量法导出了均匀圆柱形反应堆时空中子动力学方程的近似解析解,它满足反应堆运行现场所需的计算速度和精度要求,对舰船反应堆安全运行有重要意义。
3) Neutron dynamics
中子动力学
4) neutron-kinetics
中子动力学
1.
The analytic solutions of point-reactor neutron-kinetics equation with small step reactivity;
小阶跃反应性输入时点堆中子动力学方程的解析解
5) point-reactor kinetic equation
点[反应]堆动力学方程
6) fast power breeder
忆中子动力增殖[反应]堆
补充资料：快堆(见快中子增殖堆)
快堆(见快中子增殖堆)
fast-breeder reactor
l快堆堆。(fast一breeder reaetor)见快中子增殖
说明：补充资料仅用于学习参考，请勿用于其它任何用途。
参考词条