为快速求解反应堆三维时空动力学方程，克服已有方法的局限，提出了一种新的求解方法。
A new approach is presented to efficiently solve the three dimensional space time reactor dynamics equation which overcomes the disadvantages of current methods.
介绍了一种适合于求解反应堆中子动力学方程的刚性限制法。
The stiffness confinement method (SCM) for solving the reactor neutron kinetic equations is described.
介绍了一种直接利用守恒方程进行反应堆故障诊断的方法。
This paper presents a method based on conservation equations to diagnose reactor components faults.
在反应堆动力学方程中，考虑了堆体外反照中子效应，将其作为模拟缓发中子处理。
The terms for the effects of the neutrons reflected back from outside the reactor are added as extra delayed neutron terms to the reactor kinetics equation.
在反应堆物理计算中，扰动计算需要中子本征值方程的共轭方程。
Perturbation calculation in reactor physics requires the neutron adjoint eigenvalue equation.
对安装有密度锁的反应堆冷却剂系统进行了流动分析，根据流体运动方程和系统的循环流动特性，说明了密度锁的作用和具有的特性。
Based on the motion equation and flow circulation in the system, the flow analysis to reactor coolant system with density locks is given; the action and characteristics of density locks are explained.
本文用时域边界积分方程提出研究半球形核反应堆安全壳在爆炸冲击波作用下动力响应分析的计算模型。
This paper is concerned with the transient responses of semisphere containment structure of nuclear reactor to a blast wave by the boundary element method in time domain.
本文讨论基于单能静态各向同性迁移方程的原子核反应堆系统的最优控制问题。
The study on applying the algorithm of global predictive control with self-adaptive in the power control of the nuclear reactor;
本文讨论基于单能静态各向同性迁移方程的原子核反应堆系统的最优控制问题。
The study on applying the algorithm of global predictive control with self-adaptive in the power control of the nuclear reactor;
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