生产堆石墨套管污染分布研究  

Study of Contamination Distribution in Graphite Tube of Graphite Production Reactor

作　　者：黄祖程 HUANG Zucheng(Innovation R&D Center,CNNC Sichuan Environmental Protection Engineering Co.,Ltd.,Guangyuan,Sichuan Province,628000 China)

机构地区：[1]中核四川环保工程有限责任公司创新研发中心,四川广元628000

出　　处：《科技资讯》2023年第18期102-107,共6页Science & Technology Information

摘　　要：某石墨慢化水冷生产堆堆芯主要由石墨砌体和石墨套管构成,生产运行过程中石墨套管中的14C主要来源于杂质N和孔隙N2经过14N(n,p)14C反应,同时石墨套管具有较强的吸附性,长期暂存的石墨套管基体由表及里不同深度吸附的放射性核素种类和放射性核素污染水平不明。通过建立生产堆石墨套管内外表面逐层剥离方法与冷态验证,验证了逐层剥离工艺的可行性、可靠性和稳定性,获取了石墨套管内外表层逐层剥离工艺参数,实现了对放射性石墨套管逐层剥离和样品收集,并根据样品分析的结果和数据分析,初步掌握了生产堆石墨套管中放射性核素分布情况。The core of a graphite-moderated water-cooled production reactor is mainly consisted of graphite stacks and graphite sleeves.During production and operation,the 14C in graphite sleeve mainly comes from the reaction of 14N(n,p)14C between impure N and pore N2.At the same time,the graphite sleeve has strong adsorbability,and the types of radionuclides and the contamination level of radionuclidesthat the graphite sleeve matrix for long-term temporary storage adsorbs at different depths from the outside to inside are unknown.Through establishing the layer-by-layer stripping method and cold state verification of the inner and outer surfaces of the graphite sleeves of the production reactor,the feasibility,reliability and stability of the layer-by-layer stripping process is verified,the parameters of the layer-by-layer stripping process of the inner and outer surfaces of the graphite sleeves are obtained,the layer-by-layer stripping and sample collection of the radioactive graphite sleeve are realized,and the distribution of radionuclides in the graphite sleeve in the production reactor is preliminarily grasped according to samples analysis results and data analysis.

关 键 词：生产堆 石墨套管 剥离工艺 样品分析 污染分布 

分 类 号：T-19[一般工业技术]