The long-lived radionuclides radiotoxicity ranking the nuclear fuel cycle of the Belarusian NPP

N. V. Harbachova, J. A. Korchova, N. Kuzmina, N. Kulich, S. Yacko
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Abstract

Using a methodical approach to the potential biological hazard (radiotoxicity) assessment of radionuclides, computational studies and a comparative analysis of the contributions to the total radiotoxicity of long-lived fission products and actinides accumulated in the nuclear fuel cycle of the Belarusian NPP were carried out. In order to estimate correctly the 237Np isotope mass at the long-term stage of SNF management, the mathematical model of the nuclear fuel cycle of the Belarusian NPP of the code CUB was modified to take into account the transmutation chain of 241Pu, 241Am and 237Np isotopes. The initial concentrations for the main radiation-hazardous radionuclides at the time of fuel unloading from the VVER1200 reactor core are presented in the database “Radiation Characteristics of Spent Nuclear Fuel of the Belarusian NPP” developed by the authors. The database development is carried out in accordance with the recommendations of the RB-093-20 “Radiation and thermophysical characteristics of spent nuclear fuel of pressurized water power reactors and high-power channel reactors”. The main characteristics used in the nuclear fuel cycle simulation in the CUB code, such as the total mass of spent nuclear fuel (2492 tons), the number of spent fuel assemblies (5294) and the average burnup, are taken in accordance with the Spent Fuel Management Strategy of the Belarusian NPP data. It is shown that at the stage up to 100 years, the main contributors to the total radiotoxicity are the isotopes of 238Pu, 239Pu, 240Pu, 243Am, 241Pu, 241Am, 237Np, where contributions of three last of them are 0.07, 49.0 and 0.007%, respectively. But 5000 years later, the contribution of 241Am will be 0.24%, and the isotope 237Np – up to 0.1% of the total actinides radiotoxicity. The results obtained can be used to substantiate for the recovery degree requirements of 237Np, 241Pu, 241Am during the SNF of the Belarusian NPP reprocessing.
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白俄罗斯核电厂核燃料循环的长寿命放射性核素放射毒性排名
对放射性核素的潜在生物危害(放射毒性)评估采用了有系统的方法,对白俄罗斯核电站核燃料循环中积累的长寿命裂变产物和锕系元素对总放射毒性的贡献进行了计算研究和比较分析。为了准确估计SNF长期管理阶段的237Np同位素质量,对代码为CUB的白俄罗斯核电站的核燃料循环数学模型进行了修改,考虑了241Pu、241Am和237Np同位素的嬗变链。从VVER1200反应堆堆芯卸载燃料时,主要有害辐射的放射性核素的初始浓度载于作者开发的“白俄罗斯核电站乏燃料的辐射特性”数据库。数据库的开发是按照RB-093-20“压水堆和大功率通道堆乏核燃料的辐射和热物理特性”的建议进行的。CUB法规中核燃料循环模拟中使用的主要特征,如乏核燃料的总质量(2492吨)、乏燃料组件的数量(5294个)和平均燃耗,是根据白俄罗斯核电站的乏燃料管理战略数据采用的。结果表明,在100年以前,对总放射性毒性的贡献主要是238Pu、239Pu、240Pu、243Am、241Pu、241Am和237Np,其中最后3种的贡献分别为0.07%、49.0%和0.007%。但5000年后,241Am的贡献将为0.24%,而同位素237Np -占总锕系元素放射性毒性的0.1%。所得结果可为白俄罗斯核电站后处理SNF中237Np、241Pu、241Am的回收率要求提供依据。
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