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退役石墨中14C的分析

Analysis of 14C in decommissioning graphite

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【作者】 文炜但贵萍邱永梅谭昭怡

【Author】 WEN Wei;DAN Gui-ping;QIU Yong-mei;TAN Zhao-yi;Institue of Nuclear Physics and Chemistry, China Academy of Engineering Physics;

【通讯作者】 谭昭怡;

【机构】 中国工程物理研究院核物理与化学研究所

【摘要】 随着国内反应堆退役工作的逐步推进,将有大量放射性石墨需要处理或处置。石墨的处理方法与石墨的放射性源项及活度密切相关,14C是其主要源项之一。本文基于石墨高温氧化、Carb-Sorb E吸收CO2的技术路线,建立了石墨中14C的快速分析方法,前处理时长约2 h。对于0.4 g石墨样品,本方法的化学回收率可达98%以上,检出限为0.068 Bq·g-1,对3H、36Cl、60Co等干扰核素的去污因子为103~105。该方法已成功用于某研究堆退役石墨样品的分析。

【Abstract】 With the gradual advance of reactor decommissioning in China, there will be a large amount of radioactive graphite to be disposed.The disposal of graphite is closely related to its radioactive source terms and radioactivity, and 14C is one of the main source terms.Based on the technical route of high temperature oxidation of graphite and CO2 absorbed by Carb-Sorb E,a rapid analysis procedure of 14C in graphite was established.The duration of pretreatment was about 2 h.The chemical recovery of this procedure is more than 98%,and the limited detection is 0.068 Bq·g-1 for 0.4 g graphite.Decontamination factors(DFs)of major interfering radionuclides, such as 3H,36Cl, 60Co, were 103~105.This procedure has been successfully used for analysis of 14C present in graphite in a decommissioning reactor.

【关键词】 14C石墨退役分析
【Key words】 14Cgraphitedecommissioninganalysis
  • 【文献出处】 化学研究与应用 ,Chemical Research and Application , 编辑部邮箱 ,2023年08期
  • 【分类号】TQ127.11;TL943
  • 【下载频次】1
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