Abstract The macroscopic data preparation process is the essential part of the safe operation nuclear power station and despite the increasing calculation power this method stays essential in the near future. The data preparation process and mainly the assembly discontinuity factors (ADF) calculation are analysed in the paper. Developed models are connected with the C7 core of the VR-1 research reactor, which is operated by the Czech Technical University in Prague. The fuel models as well as the connection of the fuel and the reflector models are analysed. The multiplication factor and the neutron flux distribution are compared. The fuel ADF usage showed better prediction of the multiplication factor and also the neutron flux distribution. The new external iteration reflector ADF calculation method is developed, implemented and tested in the paper. The most realistic model of C7 core was used as a test case. The best results of the multiplication factor as well as the neutron flux distribution were obtained with the external iteration process ADF calculation. The multiplication factor was calculated with only 452 pcm discrepancy, more than 6600 pcm better result than without ADF and more than 3400 pcm better result than with reflector ADF calculated via SCALE Newt.

中文翻译：

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VR-1 处的径向反射器不连续因子迭代方案

摘要 宏观数据准备过程是核电站安全运行的重要组成部分，尽管计算能力不断提高，但在不久的将来，这种方法仍然必不可少。文中分析了数据准备过程，主要是装配不连续性因子（ADF）的计算。开发的模型与 VR-1 研究堆的 C7 堆芯相连，该堆由布拉格的捷克技术大学运营。分析了燃料模型以及燃料和反射器模型的连接。比较倍增因子和中子通量分布。燃料 ADF 的使用显示了对倍增因子和中子通量分布的更好预测。本文开发、实现和测试了新的外部迭代反射器 ADF 计算方法。使用最真实的 C7 内核模型作为测试用例。外迭代过程ADF计算得到了乘法因子和中子通量分布的最佳结果。计算倍增因子时只有 452 pcm 的差异，比没有 ADF 的结果好 6600 pcm 以上，比通过 SCALE Newt 计算的反射器 ADF 的结果好 3400 pcm 以上。