A detailed geometrical model of a Krško reactor core was developed using a Monte Carlo neutron transport code MCNP. The main goal of developing an MCNP core model is for it to be used in future research focused on ex-core calculations. A script called McCord was developed to generate MCNP input for an arbitrary fuel cycle configuration from the diffusion based core design package CORD-2, taking advantage of already available material and temperature data obtained in the nuclear core design process. The core model was used to calculate 3D power density profile inside the core. The applicability of the calculated power density distributions was tested by comparison to the CORD-2 calculations, which is regularly used for the nuclear core design calculation verification of the Krško core. For the hot zero power and hot full power states differences between MCNP and CORD-2 in the radial power density profile were <3%. When studying axial power density profiles the differences in axial offset were less than 2.3% for hot full power condition. To further confirm the applicability of the developed model, the measurements with in-core neutron detectors were compared to the calculations, where differences of 5% were observed.

Krško 反应堆堆芯的详细几何模型是使用蒙特卡罗中子传输代码 MCNP 开发的。开发 MCNP 核心模型的主要目标是将其用于未来专注于外核心计算的研究。一个名为 McCord 的脚本被开发用于从基于扩散的堆芯设计包 CORD-2 中生成任意燃料循环配置的 MCNP 输入，利用在核堆芯设计过程中获得的现有材料和温度数据。核心模型用于计算核心内部的 3D 功率密度分布。通过与 CORD-2 计算进行比较，测试了计算出的功率密度分布的适用性，CORD-2 计算经常用于 Krško 堆芯的核堆芯设计计算验证。对于热零功率和热全功率状态，径向功率密度分布中 MCNP 和 CORD-2 之间的差异<3%。在研究轴向功率密度分布时，对于热全功率条件，轴向偏移的差异小于 2.3%。为了进一步确认开发模型的适用性，将堆芯中子探测器的测量结果与计算结果进行了比较，其中观察到了 5% 的差异。