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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 31 | Number 2 | February 1968 | Pages 191-206
Technical Paper | doi.org/10.13182/NSE68-A18231
Articles are hosted by Taylor and Francis Online.
The energy spectra of neutrons from the the thermal-neutron-induced fission of 235U, 233U, and 239Pu have been compared by means of eight activation detectors that cover the energy range 0.8 to 16 MeV. The detectors are exposed to fission neutrons produced at the center of a 10-cm-diam spherical cavity within a heavywater moderator. Comparison of detector responses for the three spectra yield average energy ratios, 235U: 233U: 239Pu = (1): (1.021 ± 0.005): (1.039 ± 0.002). Differences between the normalized spectra are most pronounced at high energies as exemplified by the relative 239Pu: 235U flux ratios 1.17 for 6 < E < 11 MeV and 1.35 for E > 11 MeV. Spectral indexes for the 235U fission spectrum, based on measurements with monoenergetic neutrons, show progressively fewer neutrons above 6 MeV than given by the usual Maxwellian description of the fission spectrum, χ235U(E) = (0.770)E1/2 exp (−0.775E). At lower energies, the observed spectral indexes involving the 235U, Np, and 238U fission detectors are significantly discrepant with those predicted.