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.

Volume Subject Area:
Radiation Protection and Nuclear Technology Applications
Keywords:
cask, spent fuel transport, package operation, dose rate, risk control
Topics:
Radiation (Physics), Risk control, Spent nuclear fuels
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