| 近海核电厂核素地下水释放通量的模型计算方法 |
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| 引用本文： | 朱君,李婷,陈超,谢添,张艾明.近海核电厂核素地下水释放通量的模型计算方法[J].吉林大学学报(地球科学版),2021,51(1):201-211. |
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| 作者姓名： | 朱君 李婷 陈超 谢添 张艾明 |
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| 作者单位： | 中国辐射防护研究院核环境模拟与评价技术重点实验室, 太原 030006 |
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| 基金项目： | 国家国防科技工业局核能开发项目（2016-08） |
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| 摘 要： | 为了定量计算陵区近海核电站排水管线泄漏情景下核素通过地下水途径向海洋环境的释放通量,以某近海核电站为例进行研究。首先,应用GOCAD软件建立三维地形地质模型,刻画地层的分布、剥蚀以及倾向等特点;然后,运用地下水数值模拟软件FEFLOW精细刻画丘陵区地下水系统的补给、径流和排泄特征;最后,以不被吸附滞留的核素3H和被吸附滞留的核素90Sr、137Cs为对象,通过实验测定了90Sr、137Cs在不同岩土介质中的分配系数,模拟计算了排水管线连续渗漏60 a后3H、90Sr、137Cs在地下水中的放射性分布及释放。结果表明:3H迁移速度基本与地下水流速一致,地下水中的最大放射性浓度为0.285 0 Bq/L,第20 000天时向收纳水域的释放通量达到最大值,约526 Bq/d;90Sr吸附性能相对较弱,最大迁移距离约80 m,地下水中的最大放射性浓度为0.032 1 Bq/L;137Cs吸附能力较强,相当长的时间内被滞留在管线附近,地下水中最大放射性浓度分别为6.840×10-3 Bq/L,释放通量为0 Bq/d。由弥散度的不确定分析可知,弥散度越大,地下水中3H的最大放射性浓度越小,向海洋环境的释放通量越多。
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| 关 键 词： | 近海核电厂 丘陵区 地下水 释放通量 核素迁移 |
| 收稿时间： | 2019-07-14 |
Model Calculation Method of Radionuclide Groundwater Release Flux of Offshore Nuclear Power Plants |
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| Zhu Jun,Li Ting,Chen Chao,Xie Tian,Zhang Aiming.Model Calculation Method of Radionuclide Groundwater Release Flux of Offshore Nuclear Power Plants[J].Journal of Jilin Unviersity:Earth Science Edition,2021,51(1):201-211. |
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| Authors: | Zhu Jun Li Ting Chen Chao Xie Tian Zhang Aiming |
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| Institution: | Key Laboratory of Nuclear Environmental Simulation and Evaluation Technology, China Institute for Radiation Protection, Taiyuan 030006, China |
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| Abstract: | In order to quantitatively calculate the release flux of radionuclides to marine environment through groundwater under the situation of drainage pipeline leakage in hilly area, an offshore nuclear power station was taken as an example. Firstly, a three-dimensional topographic geological model was established by using GOCAD software to describe the distribution, denudation,and tendency of strata; Secondly, a three-dimensional hydrogeological model was built with FEFLOW to generalize the characteristics of recharge, runoff,and discharge of groundwater system in hilly area; Finally, the distribution coefficients of 90Sr、137Cs in different groundwater rock and soil media were measured experimentally. After that, the concentration distribution of radionuclides in groundwater after continuous leakage of drainage pipes for 60 a was simulated and calculated. The result shows that the migration velocity of 3H is basically the same as that of groundwater. The maximum concentration of 3H in groundwater is 0.285 0 Bq/L, and the maximum release flux to the receiving water reaches about 526 Bq/d on the 20 000th day. The maximum migration of 90Sr is about 80 m, and the maximum radioactive concentration in groundwater is 0.032 1 Bq/L. 137Cs is retained near the pipeline for a long time because of its strong adsorption capacity, its maximum radioactive concentration in groundwater is 6.840×10-3 Bq/L, and the release flux is 0 Bq/d. Based on the analysis of dispersion uncertainty, the greater the dispersion is, the smaller the maximum radioactive concentration of 3H is in groundwater, and the greater the release flux is to marine environment. |
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| Keywords: | offshore nuclear power plants hilly area groundwater release flux radionuclide migration |
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