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Dose Distribution in the Spent Fuel Package Operations and the Radiation Risk Control

[+] Author Affiliations
Gang Lü, Meng Wei, Zhen Zhang, Shiyuan Li, Xue Han

CNNC Everclean, Beijing, China

Paper No. ICONE21-16854, pp. V001T04A034; 6 pages
doi:10.1115/ICONE21-16854
From:
  • 2013 21st International Conference on Nuclear Engineering
  • Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications
  • Chengdu, China, July 29–August 2, 2013
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5578-2
  • Copyright © 2013 by ASME

abstract

In this paper, NAC-STC (spent fuel transport cask) package operation is studied. The calculated / measured doses of different parts of the cask surface (or 1 m and 2 m away) in the course of package operation are analyzed. The radiation risk control methods are proposed to protect the operators exposed in the high dose area.

Copyright © 2013 by ASME

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