Methods of determining the efficiency of the system that controls the seal-tightness of fuel-rod cladding and localizes FA with leaky fuel rods in a fast reactor are examined. It is shown that the design procedure has significant limitations. A procedure for numerical modeling of the transport of delayed-neutron precursors was developed to take account of the special features of liquid-metal coolant flow. A special computational module FV-BN was developed within the framework of the FlowVision software package. The computational results obtained for the concentration distribution of delayed-neutron precursors are transferred into the deterministic transport code TORT in order to obtain the spatial-energy distribution of the neutron flux density in a three-dimensional geometry. The procedure was verified on full-scale reactor problems by simulating the flow-through parts of the upper mixing chamber of the fast reactor.

检验了确定系统效率的方法，该系统控制燃料棒包壳的密封性并使快速反应堆中的燃料棒泄漏的FA局部化。结果表明，设计程序有很大的局限性。考虑到液态金属冷却剂流的特殊特征，开发了一种用于延迟中子前体传输的数值模型程序。在FlowVision软件包的框架内开发了一个特殊的计算模块FV-BN。为获得延迟中子前体的浓度分布而获得的计算结果被转移到确定性传输码TORT中，以便获得三维几何形状中子通量密度的空间能分布。