用于区分后处理厂中、低放废水的γ探测器选型方案  

Gamma Detector Selection Scheme for Liquid Effluent Detection in Nuclear Fuel Reprocessing Plant

作　　者：严修 夏虹[1,2] Yan Xiu;Xia Hong(Key Laboratory of Nuclear Safety and Advanced Nuclear Energy Technology,Ministry of Industry and Information Technology,Harbin Engineering University,Harbin,150001,China;Fundamental Science on Nuclear Safety and Simulation Technology Laboratory,Harbin Engineering University,Harbin,150001,China)

机构地区：[1]哈尔滨工程大学核安全与先进核能技术工信部重点实验室,哈尔滨150001 [2]哈尔滨工程大学核安全与仿真技术国防重点学科实验室,哈尔滨150001

出　　处：《仪器仪表用户》2022年第1期57-60,70,共5页Instrumentation

摘　　要：本研究基于某核废料处理厂的中、低放废水能谱数据,运用仿真软件对不同的探测场景进行建模和计算,目的在于确定用于区分中、低放废水的γ探测器选型方案及相应的取样方案。研究内容包括:(1)利用废水能谱计算放射性粒子通量;(2)计算取样体积;(3)对不同的探测器进行选型分析。This study is based on the energy spectrum data of the middle-level and low-level radioactive liquid effluent of a nuclear waste treatment plant, and uses simulation software to model and calculate different detection scenarios. The purpose of this study is to introduce the gamma detector selection scheme for distinguishing middle-level and low-level radioactive liquid effluent. The research content includes:(1)Calculate the flux of radioactive particles by using the liquid effluent energy spectrum;(2)Calculate the sampling volume;(3)Select and analyze different gamma detectors.

关 键 词：中低放废水 Γ探测器 选型方案 

分 类 号：TL941[核科学技术—辐射防护及环境保护]