Author:
Rudychev V.G.,Azarenkov N.A.,Girka I.O.,Rudychev Y.V.
Abstract
A model of the transport container intended for transportation of spent nuclear fuel (SFN) is studied. The passage of γ-quanta from the major long-lived isotopes is examined. The radiation shields made of iron, lead and
depleted uranium, which are equivalent in mass to the thickness of iron of 15 to 35 cm is considered. The calculations are carried out using the Monte Carlo method (in MCNP and PHITS packages). The change in the characteristics of γ-radiation beyond the shields, made of different materials and with different thicknesses, is determined. For SNF from WWER-1000 with the thicknesses up to ~ 21 cm, the shield made of lead and uranium is shown to be more effective. If the thickness of the shield exceeds ~ 21 cm, then the shield made of iron is more
effective. Increasing the thickness of the shields above 25 cm is shown to be inefficient, since the shields mass increases but the dose rate decreases slightly in this case.
Publisher
Problems of Atomic Science and Technology
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