反应堆退役石墨中^(14)C分析制样实验系统研制  

Development on Analysis and Making Sample Experiment System of ^(14)C in Graphite in Decommissioning of Reactor

作　　者：邱永梅[1] 王萍[1] 但贵萍[1] 文炜[1] 孙耀中[1] 

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：《原子能科学技术》2010年第B09期119-123,共5页Atomic Energy Science and Technology

摘　　要：为分析反应堆退役废物石墨中的14C含量,设计制作了一套14C高温催化氧化制样实验系统,在实验室中对该系统的处理能力和运行功能进行了部份实验验证。结果表明:在标气流速为1L/min、催化氧化炉800℃时,对CO催化氧化能力为96%;2mol/L的NaOH溶液对CO2的吸收能力可达99%(其中,一级吸收为67%,二级32%);空气流速为1L/min、高温解吸室850℃,1h后石墨样品分解率为99.99%;使用CaCO3固体粉末悬浮液闪测量法时,CaCO3的化学回收率为99%。To analyze 14C content in graphite of reactor retirement waste, a suit of making sample experiment system with high temperature catalysis and oxidation was designed. The treatment ability and working function of this system were confirmed partly in the lab. The results show that the catalysis and oxidation ability is 96% with 1 L/min gas flux and 800 ℃ oxidation temperature, and the ability of 2 mol/L NaOH solution absorption to CO2 is 99% （first absorption 67%, second absorption 32%）. Determinating by fluid scintillation of CaCO3 solid powder suspended solution, the recovery rate is 99%.

关 键 词：反应堆 退役 石墨 14C 分析测量 

分 类 号：O657.4[理学—分析化学]