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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.
S. K. Davis, J. A. De Juren, M. Reier
Nuclear Science and Engineering | Volume 23 | Number 1 | September 1965 | Pages 74-81
Technical Paper | doi.org/10.13182/NSE65-A19260
Articles are hosted by Taylor and Francis Online.
Measurements of the shape of the fundamental mode of a thermalized neutron pulse in graphite for rectangular stacks has yielded a value of the extrapolation length, d = 1.825 ± 0.025 cm. The pulsed-neutron decay constants in graphite have been measured over a buckling range from 1.946 × 10−3 to 1.230 × 10−2 cm −2 and fitted to three- and four-term power series in the buckling. To fit points at bucklings greater than 6.0 × 10−3 cm−2, a cubic fit is necessary. An iterative method of fitting the decay constants results in an extrapolation length of 1.78 ± 0.01 cm. The diffusion constant was (2.0896 ± 0.0093) × 105cm2/sec, and the diffusion cooling constant was (3.77 ± 0.35) × 106 cm4/sec at a density of 1.689 g/cm3. A technique of correcting the decay constants for the effect of spectral cooling has been developed. The decay constants corrected to room temperature can be fitted as a linear function of the buckling. This method interates on the heat-transfer coefficient, γ, and gives a value of γ = 1633 ± 89 sec−1 for graphite. The heat-transfer coefficient relates the rate of energy transfer from a moderator to a cooled-neutron spectrum. With this approach the entire buckling range can be fitted with three parameters.