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反应堆退役石墨中36Cl的分析 被引量:1

Analysis of 36Cl in radioactive graphite from decommission nuclear reactor
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摘要 在反应堆退役中,为有效开展放射性石墨的处理,需对石墨中放射性核素进行测量。36Cl是石墨中一种重要的放射性核素,其半衰期长、环境中易迁移,无法直接测量其活度。为建立满足反应堆退役石墨中36Cl分析的方法,本文将堆退役石墨样品完全溶解后,再通过共沉淀和离子交换去除干扰核素,获得36Cl待测液,然后用液闪测量36Cl的活度。当石墨样品量为0.2g时,该方法的化学回收率为88.7%,最低可探测活度为67mBq·g-1,对主要干扰核素有较高的去除能力。该方法可用于反应堆退役石墨中36Cl的分析。 For disposing irradiated graphite more availably,it is important tomeasurethe activity of graphite from reactor.36Cl with long-life and high mobility in environment is one of the important radionuclides in irradiated graphite.It can’t be detected without chemical separation.A method for analysis of 36Cl in irradiated graphite has been established.After graphite samples were dissolved completely,precipitation and ion-exchange chromatography were used to remove interfering radionuclides.The purified 36Cl was measured by liquid scintillation counting.The chemical recovery of Cl is about 88.7%,and the minimum detectable activity for 36Cl is 67mBq·g-1 for 0.2g graphite samples.The decontamination factors for major interfering radionuclides are high in the whole procedure.The method can be used to determine 36Cl in graphite from reactor.
作者 文炜 但贵萍 邱永梅 谭昭怡 WEN Wei;DAN Gui-ping;QIU Yong-mei;TAN Zhao-yi(Institue of Nuclear Physics and Chemistry,China Academy of Engineering Physics,Mianyang 621900,China)
出处 《化学研究与应用》 CAS CSCD 北大核心 2020年第7期1255-1259,共5页 Chemical Research and Application
关键词 研究堆 石墨 36Cl 分析 research reactor graphite 36Cl analysis
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