This work is aimed at developing an advanced model of the Slovak VVER-440/V-230, reactor in the MCNP code, to calculate induced activity in ex-vessel structural components and to validate obtained results to achieve an effective calculation tool for decommissioning purposes. A survey of the V1 NPP operating history revealed that after 12 fuel cycles the shielding assemblies were placed at the core boundary positions thereby reducing the core and decreasing the neutron flux on reactor pressure vessel as well as in adjacent ex-vessel components. Representative fuel cycles were selected for given periods. Model of the V1 reactor at the core level was developed, covering in-vessel and ex-vessel components. The activation calculation of the reactor concrete shaft at the sample volume location was performed using the MCNP5 code with the ENDF/B-VII cross-section library. Activities of selected radionuclides were determined and verified by measurements of samples at the Slovak University of Technology.

这项工作旨在开发斯洛伐克 VVER-440/V-230 反应堆的高级模型，MCNP 代码中的反应堆，计算前船结构部件中的诱导活动并验证获得的结果，以实现退役目的的有效计算工具. 对 V1 核电厂运行历史的调查显示，在 12 次燃料循环后，屏蔽组件被放置在堆芯边界位置，从而减少堆芯并降低反应堆压力容器以及相邻的外容器组件中的中子通量。为给定时期选择代表性燃料循环。开发了堆芯级V1反应堆模型，涵盖了船内和船外部件。使用带有 ENDF/B-VII 横截面库的 MCNP5 代码执行样本体积位置处反应器混凝土竖井的活化计算。斯洛伐克理工大学通过对样品的测量来确定和验证选定放射性核素的活性。