退役石墨中^(14)C的分析  

Analysis of^(14)C in decommissioning graphite

作　　者：文炜[1] 但贵萍[1] 邱永梅[1] 谭昭怡[1] 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)

机构地区：[1]中国工程物理研究院核物理与化学研究所,四川绵阳621900

出　　处：《化学研究与应用》2023年第8期1864-1869,共6页Chemical Research and Application

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,^(14)C是其主要源项之一。本文基于石墨高温氧化、Carb-Sorb E吸收CO_(2)的技术路线,建立了石墨中^(14)C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^(3)H、^(36)Cl、^(60)Co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。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^(14)C is one of the main source terms.Based on the technical route of high temperature oxidation of graphite and CO_(2)absorbed by Carb-Sorb E,a rapid analysis procedure of^(14)C 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^(3)H,^(36)Cl,^(60)Co,were 103~105.This procedure has been successfully used for analysis of^(14)C present in graphite in a decommissioning reactor.

关 键 词：^(14)C 石墨 退役 分析 

分 类 号：O657[理学—分析化学]