某反应堆放射性存留量实验测定  

Experimental Determinaton of a Decommissioned Nuclear Reactor

作　　者：林晓玲[1] 杜德福[2] 陈迎锋[1] 

机构地区：[1]92609部队 [2]中国核动力研究设计院

出　　处：《辐射防护》2010年第4期232-235,258,共5页Radiation Protection

摘　　要：采用实验室取样分析方法确定某反应堆(压水堆)退役后堆内部件、压力容器和一次屏蔽等活化部件中放射性存留量活度。给出了活化样品中主要放射性核素和辐射特点,介绍了实验中采用的仪器设备和测量方法,以及采用样品活度推导各部件总活度的方法,并给出了反应堆停堆8年各部件中的放射性活度。取样分析表明,反应堆运行终止时放射性存留量主要集中在堆内部件中,占总存留量的94%,压力容器放射性存留量占6%,与之相比,一次屏蔽中的放射性存留量可忽略。The radioactive inventory was determined by sampling and laboratory analysis for the activated components such as the reactor internals,the pressure vessel and the neutron shied tank etc at a decommissioned nuclear reactor （PWR）.The most important radionuclides and their activation reactions considered were showed.The techniques and instruments utilized in laboratory analysis were provided.Lastly,radionuclide residues for the main activated components were estimated.It was shown that radionuclide residues were mainly hold in the reactor internals,which represents 94%,and the pressure vessel 6%,the quantity of residues in primary shields was little.

关 键 词：反应堆 退役 放射性 存留量 实验 

分 类 号：TL24[核科学技术—核燃料循环与材料]