An analytic solution is given for a system of first-order inhomogeneous linear differential equations describing the mass transfer of fission products in radioactive decay chains of arbitrary complexity and length by means of a system of an infinite number of working zones separated by radiation safety barriers. The computational procedure is implemented in the TARUSA system of computer codes, making it possible to take into account the individual behavior of different fi ssion products as they pass through radiation safety barriers and the arbitrary dependence of the basic initial data on the operating time of the reactor. The TARUSA codes possess their own libraries of nuclear-physical constants. A comparison is made with the normative example of the calculation of the residual power release from irradiated fuel from the international standard ISO 10645.

中文翻译：

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计算多区反应堆问题中裂变产物传质的方法

给出了一个一阶非齐次线性微分方程组的解析解，该方程组描述了任意复杂性和长度的放射性衰变链中裂变产物的质量传递，该系统通过由辐射安全屏障分隔的无限数量的工作区组成。计算程序在 TARUSA 计算机代码系统中实施，从而可以考虑不同裂变产物通过辐射安全屏障时的个体行为以及基本初始数据对操作时间的任意依赖性。反应堆。TARUSA 代码拥有自己的核物理常数库。