The water-cooled WWR-K research reactor has been operating since 2016 using low-enrichment uranium fuel. In order to maintain high levels of generated power and reactivity margin sufficient for a 21-day operation cycle, the water-cooled core reflector of neutrons was gradually, depending on the fuel burnup, replaced by a beryllium one in order to prevent decreasing of the reactor performance. A series of calculation studies are performed with a simulation of the core region of the WWR-K reactor using an MCNP transport code including determination of neutron flux density, reactivity, efficiency of the control rods of the control and protection systems, as well as kinetic parameters critical for ensuring safe reactor operation. The calculated curves of the principal performance characteristics of the WWR-K reactor are presented and analyzed in terms of their use in scientific research and their effect on the reactor operation safety.

自2016年以来，水冷WWR-K研究堆一直在使用低浓铀燃料运行。为了维持足够高的发电功率和足够的反应性余量，以进行21天的工作循环，根据燃料的燃烧情况，逐渐将中子的水冷堆芯反射器替换为铍，以防止燃料中子的减少。反应堆性能。使用MCNP传输代码对WWR-K反应堆核心区域进行仿真，进行了一系列计算研究，包括确定中子通量密度，反应性，控制和保护系统控制杆的效率以及动力学对确保反应堆安全运行至关重要的参数。