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60 Co 放射源运输容器屏蔽性能检测

孙洪超 李国强 闫峰 庄大杰 孙树堂 王学新

同位素Issue(2):75-80,6.
同位素Issue(2):75-80,6.DOI:10.7538/tws.2015.28.02.0075

60 Co 放射源运输容器屏蔽性能检测

Shielding Performance Measurements on Container for 60 Co Radioactive Sources Transport

孙洪超 1李国强 1闫峰 1庄大杰 1孙树堂 1王学新1

作者信息

  • 1. 中国辐射防护研究院,山西 太原 030006
  • 折叠

摘要

Abstract

Some radioactive sources are often used in irradiation industry and radiothera‐py ,such as 60Co ,137Cs ,131I ,32P ,153Sm ,99Mo ,90Sr ,89Sr and so on .The radiation includeα、β、γ and n .The radiation from γ sources are the mostly concerned during the transporting of radioactive sources .The shielding performance measurements on con‐tainer for 60Co radioactive sources transport were discussed by using both Monte Carlo method simulation calculation and experiment measurement . Some important factors w as discussed w hich could affect the results of shielding performance measurements . The layout of radioactive sources had a important impact on the monitoring results of the external radiation levels of radiation sources transport container .The results affor‐ded the contribution to the improvement of the radiation monitoring and management of radioactive material transportation package .

关键词

辐射水平监测/辐射屏蔽性能检测/放射源运输容器

Key words

radiation levels monitoring/shielding performance measurements/radioac-tive sources transport container

分类

能源科技

引用本文复制引用

孙洪超,李国强,闫峰,庄大杰,孙树堂,王学新..60 Co 放射源运输容器屏蔽性能检测[J].同位素,2015,(2):75-80,6.

同位素

OACSTPCD

1000-7512

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