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3D-printed tool at SRS makes quicker work of tank waste sampling
A 3D-printed tool has been developed at the Department of Energy’s Savannah River Site in South Carolina that can eliminate months from the job of radioactive tank waste sampling.
J. J. Rush, D. W. Connor, and R. S. Carter
Nuclear Science and Engineering | Volume 25 | Number 4 | August 1966 | Pages 383-389
Technical Paper | doi.org/10.13182/NSE66-A18558
Articles are hosted by Taylor and Francis Online.
The leakage flux from an 18 × 18 in. cylinder of D2O with a beam of pile neutrons incident at its center has been studied at D2O temperatures from 22° to 293°K. Intensities through beryllium and graphite filters, as well as indium foil transmissions, have been measured to determine cold-neutron fractions and neutron temperatures for the emerging spectra. The results of these measurements show that large volumes of D2O ice can be useful as low-temperature moderators in reactors. The percentage of leakage neutrons with λn ≥ 3.95 Å is 21% at 22°K, a 20-fold increase over the fraction at 293°K, and about twice the value at 100°K. The neutron temperature of the leakage spectrum, calculated from the transmission data assuming a Maxwellian distribution, decreases with moderator temperature, reaching a value of about 75° for D2O at 22°K. An abrupt increase in the fraction of cold neutrons is observed at the D2O freezing point, which appears to reflect a change in the transport rather than the moderating properties of the D2O, due to a decrease in the cross section for long-wavelength neutrons.