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Shielding Research of Cobalt Adjuster Rod Transport Cask

Wang Bingheng,Xue Na,Mao Yawei(China Nuclear Power Engineering Co.,LTD.,Beijing 100840)  
Dose rates at the surface of adjuster rod transport cask were calculated with MCNP code and MCAM code.The calculation results were compared with national standard to estimate shielding design of the cask.To meet the requirement of the standard,original design of the cask was updated through the calculation of these codes.To reduce the radiation level,temporary shielding for the gap(between shielding door and main cask) was applied and 5 cm shielding layer of depleted uranium was applied to the side shield instead of 5 cm lead layer.According to the results,new shielding design of transport cask can meet the national standard.The measuring results show that the design of the cask is reasonable and reliable.
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