The possibilities of using partial neutron-transport equations, as compared with the classical system of equations, to estimate the temporal behavior of a fast reactor, for which computational studies have been performed on test models of the MET-1000 and MOX-1000 reactors developed as part of the Gen-IV project, are analyzed. The movement of the control rods was modeled as a reason for the appearance of nonstationary processes. The effects of reactivity in the indicated reactor models were also estimated by solving stationary problems, i.e., asymptotic estimation of the reactivity obtained by solving the stationary homogeneous neutron-transport equations, and by analyzing the solutions of a nonstationary problem via the inverse equation of kinetics. It is shown that both in computational modeling and in experiments the special features in determining the effects of reactivity and the efficiency of the control rods in fast reactors are due to delayed neutrons and the working region of the neutron spectrum.

中文翻译：

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快堆的动力学特征

与经典方程组相比，使用部分中子输运方程来估计快堆时间行为的可能性，为此已经对开发的 MET-1000 和 MOX-1000 反应堆的测试模型进行了计算研究作为 Gen-IV 项目的一部分，进行了分析。控制棒的运动被建模为非平稳过程出现的原因。反应性在指定反应堆模型中的影响也通过求解稳态问题来估计，即通过求解稳态齐次中子输运方程获得的反应性的渐近估计，以及通过动力学的逆方程分析非平稳问题的解.