Determination of volume of radioactive waste in activated VVER-1200 reactor structures

M. Zhemzhurov, G. M. Zhmura, I. Rubin, N. M. Dneprovskaya, N. A. Tetereva, I. V. Rudenkov, L. F. Babichev
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Abstract

The results of calculation studies of the amount of solid high-level, intermediate-level, low-level, very lowlevel radioactive waste (HLW, ILW, LLW, VLLW, respectively) generated during neutron activation of structural materials adjacent to the core of the VVER-1200 reactor plant, depending on the time after the final stopping it. An assessment of the volumes of radioactive waste (RAW) of activation origin generated over 60 years of operation of a VVER-1200 type reactor was carried out on the basis of computational studies of the induced activity of structural and protective materials using reactor and Monte Carlo program codes (SERPENT 2, TVS-M, DYN3D , MCU-PD). Specific activities for each isotope, total specific activities and activities, masses and volumes of activated structural and protective reactor materials for various categories of radioactive waste were calculated after the specified period of operation of VVER-1200 and over time after the final shutdown of the reactor. The obtained dependences of changes in the masses and volumes of activated materials over time after the final shutdown of the reactor make it possible to determine these parameters of materials separately for each category of radioactive waste and in total at any point in time. Thus, the masses of activated materials related to radioactive waste will decrease by 264 tons (from 713 to 449 tons) over 200 years of aging, and the volumes will decrease by 74.3 m3 (from 169 to 94.7 m3). Forecast quantitative data on the volumes and mass of activated reactor structures, depending on the duration of their exposure after the final shutdown of the power unit, will make it possible to develop technical proposals, forecast plans and schedules for organizing a radioactive waste management system during the decommissioning of the VVER-1200 reactor plant, as well as possible technological and design solutions for the disposal system for these radioactive waste.
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确定活化 VVER-1200 反应堆结构中放射性废物的体积
对 VVER-1200 型反应堆厂房堆芯附近的结构材料在中子活化过程中产生的高放射性、中放射性、低放射性和极低放射性固体废物(分别为高放射性废物、中放射性废物、低放射性废物和极低放射性废物)数量的计算研究结果,取决于最终停止后的时间。在使用反应堆和蒙特卡洛程序代码(SERPENT 2、TVS-M、DYN3D、MCU-PD)对结构材料和保护材料的诱导活度进行计算研究的基础上,对 VVER-1200 型反应堆运行 60 年期间产生的活化源放射性废物(RAW)量进行了评估。在 VVER-1200 型反应堆规定的运行期之后,以及在反应堆最终关闭之后的一段时间内,对各类放射性废物的每种同位素的特定放射性活度、总特定放射性活度和放射性活度、活化反应堆结构材料和保护材料的质量和体积进行了计算。根据反应堆最终关闭后活化材料的质量和体积随时间变化的关系,可以分别确定各类放射性废物的这些材料参数以及任何时间点的总参数。因此,在 200 年的老化过程中,与放射性废物有关的活化材料的质量将减少 264 吨(从 713 吨减少到 449 吨),体积将减少 74.3 立方米(从 169 立方米减少到 94.7 立方米)。关于活化反应堆结构的体积和质量的定量预测数据(取决于其在动力装置最终关闭后的暴露时间)将使我们有可能制定技术建议、预测计划和时间表,以便在 VVER-1200 反应堆厂退役期间组织放射性废物管理系统,并为这些放射性废物的处置系统制定可能的技术和设计方案。
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