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干冰去污在核电站换料相关设施中应用方案的初步研究

Research on Decontamination of Dry Ice Technology in Refueling Related Facilities of Nuclear Power Plant
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摘要 干冰技术的去污效率高、基材损伤小、二次废物量少,在核设施的去污实践中越来越多的受到重视。由于核电站反应堆换料系统的去污比较常见,通过对反应堆换料水池、乏燃料贮存运输容器的去污需求分析,设计一套干冰去污装置,实现对核设施的有效去污,满足人员操作和设备运输的要求;其去污过程和最终二次废物产量也遵循了废物最小化的原则,且环保高效,是未来放射性去污的重要发展方向。 Dry ice decontamination technology has attracted more and more attendion in the decontamination practice of nuclear facilities due to its high decontamination efficiency,less damage to the substrate and less secondary waste.Because of more decontamination times of reactor refueling system in nuclear power plant,through the analysis of decontamination requirements of reactor cavity and spent fuel shipping shielded cask,a set of dry ice decontamination device is designed to achieve effective decontamination of nuclear facilities,and meet the requirements of personnel operation and transportation.The decontamination process and final secondary waste production also follow the principle of waste minimization which is an important development direction of radioactive decontamination in the future due to its environmental protection and high efficiency.
作者 王鹏 邵睿 曾珍 WANG Peng;SHAO Rui;ZENG Zhen(China Nuclear Power Engineering Co.,Ltd.,Beijing 100840,China;Nuclear and Radiation Safety Center,Beijing 100082,China)
出处 《价值工程》 2022年第9期77-80,共4页 Value Engineering
基金 中核集团重点专项“乏燃料金属干法贮存容器研制(第二阶段)”,项目编号:KY1770。
关键词 干冰去污 反应堆换料系统 乏燃料贮存运输容器 闭环操作 dry ice decontamination reactor refuelling system spent fuel shipping shielded cask closed-loop operation
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