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Spent fuel transfer project completed at INL
Work crews at Idaho National Laboratory have transferred 40 spent nuclear fuel canisters into long-term storage vaults, the Department of Energy’s Office of Environmental Management has reported.
E. Aalto and Å. Krell
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 433-440
Technical Paper | doi.org/10.13182/NSE67-A18282
Articles are hosted by Taylor and Francis Online.
Neutron and gamma-ray attenuation have been studied in a cylindrical duct, length-to-diameter ratio = 7, partly (36 vol%) filled by a helical (screw-like) steel plug with an adjustable number of turns. The total neutron leakage through the duct decreased by a factor of 6 when the number of turns increased from 0 to 0.5; and by an additional factor of 3 in going from 0.5 to 2 turns (saturation value). The leakage with less than 0.5 turns is governed by the fast flux and above 0.5 turns by the epithermal flux., It is shown that the neutron attenuation (in the saturated case) can be satisfactorily predicted by homogenizing the plug and by combining the attenuation calculated in an infinite layer thus obtained with that predicted in a circular duct. The prerequisite is that the attenuation curves obtained are displaced in the streaming direction by the diameter of the duct., The attenuation of gamma rays in the saturation case (≈3 turns) equals that predicted in a homogenized infinite material without the duct attenuation.