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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.
William G. Davey
Nuclear Science and Engineering | Volume 26 | Number 2 | October 1966 | Pages 149-169
Technical Paper | doi.org/10.13182/NSE66-A28158
Articles are hosted by Taylor and Francis Online.
The published cross sections of 232Th, 233U, 234U, 235U, 236U, 237Np, 238U, 239Pu, 240Pu, 241Pu, and 242Pu from 1 keV to 10 MeV have been carefully studied to select best cross sections for fast reactor analysis. Frequently, the measurement is not of the absolute cross section but of the ratio between the unknown and some reference cross section; thus, in comparing measurements, it is important to determine if the same reference data were used in all cases. In this study, emphasis has been placed on determining the reference data used and, where necessary, the published data have been revised to accord with more accurate, currently accepted cross sections. Thus, it is believed that a consistent set of cross-section data has been derived. Some cross checks have been made by comparing calculations based on the selected cross sections with integral measurements in broad fast-neutron spectra. The study shows the great importance of the 235U fission cross section in deriving other cross sections and emphasizes the necessity of re-evaluating nearly all fission cross sections, if it proves necessary to revise the 235U data.