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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.
James A. Grundl
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 39-53
Technical Paper | doi.org/10.13182/NSE67-A17241
Articles are hosted by Taylor and Francis Online.
Eight activation detectors, 235U(n, f), Np(n, f), 238U(n,f), P(n, p), Al(n, p), 56Fe(n, p), Al(n, α), and 63Cu(n, 2n) are placed on a firm experimental foundation to prepare for the investigation of fission-neutron spectra in Part II. Gross beta-gamma counting with methane-flow counters is employed to achieve the exceptional stability of detector response required for spectrum determinations. Calibration and specification of detector excitations are based on relative cross-section measurements performed at the Los Alamos Van de Graaff. The latter have been tailored to supplement existing cross-section information and to aid in its evaluation. Deduced detector excitations are specified in fifty energy groups with uncertainties assigned in a separate seven-group excitation structure appropriate for the investigation of distributed neutron spectra.