The paper presents a conceptual design of a 10 MW multipurpose nuclear research reactor (MPRR) loaded with the low-enriched uranium (LEU) VVR-KN fuel type. Neutronics and burnup calculations have been performed using the REBUS-MCNP6 linkage system code and the ENDF/B-VII.0 data library. The core consists of 36 fuel assemblies: 27 standard fuel assemblies and 9 control fuel assemblies with the uranium density of 2.8 gU/cm³ and the ²³⁵U enrichment of 19.75 wt.%. The cycle length of the core is 86 effective full-power days with the excess reactivity of 9600 and 1039 pcm at the beginning of cycle and the end of cycle, respectively. The highest power rate and the highest discharged burnup of fuel assembly are 393.49 kW and 56.74% loss of ²³⁵U, respectively. Thermal hydraulics analysis has also been conducted using the PLTEMP4.2 code for evaluating the safety parameters at a steady state of the hottest channel. The maximum temperatures of coolant and fuel cladding are 66.0°C and 83.0°C, respectively. This value is lower than the design limit of 98°C for cladding temperature. Thermal fluxes at the vertical irradiation channels and the horizontal beam ports have been evaluated. The maximum thermal fluxes of 2.5 × 10¹⁴ and 8.9 ×10¹³ n·cm⁻²·s⁻¹ are found at the neutron trap and the beryllium reflector, respectively.

中文翻译：

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使用VVR-KN燃料的10 MW多功能研究堆的概念设计

本文介绍了一种装载有低浓铀VLE-KN燃料类型的10 MW多用途核研究堆（MPRR）的概念设计。使用REBUS-MCNP6链接系统代码和ENDF / B-VII.0数据库执行了中子学和燃耗计算。核心包括36个燃料组件：27个标准燃料组件和9个控制燃料组件，铀密度为2.8 gU / cm ³，而²³⁵ U浓缩度为19.75 wt。％。磁芯的循环长度为86个有效全功率日，在循环开始和循环结束时的反应性分别为9600和1039 pcm。燃料组件的最高功率和最高燃尽量为393.49 kW，损耗^235的56.74％U，分别。还使用PLTEMP4.2代码进行了热力学分析，以评估最热通道的稳态下的安全参数。冷却液和燃料包壳的最高温度分别为66.0°C和83.0°C。该值低于熔覆温度的设计极限98°C。已经评估了垂直照射通道和水平光束端口的热通量。在中子阱和铍反射器处分别发现最大热通量为2.5×10 ¹⁴和8.9×10 ¹³  n·cm ^-2 ·s ^-1。