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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. Tassan
Nuclear Science and Engineering | Volume 26 | Number 2 | October 1966 | Pages 271-276
Technical Paper | doi.org/10.13182/NSE66-A28169
Articles are hosted by Taylor and Francis Online.
Thermal spectrum measurements in 1% enriched uranium, 0.387-in. diam rod lattices, light water moderated, have been performed by the lutetium activation method in order to test the usefulness of this technique in not-well-thermalized lattices. Dysprosium-164 and 175Lu were used as reference thermal-neutron detectors. The experimental results are presented as the average values of the normalized (lattice/Maxwellian) activation ratios of 176Lu/Dy and 176Lu/ 175Lu with the pertinent cadmium-ratios, in the fuel and in the moderator over the H2O/U range from 1:1 to 4:1. The agreement with the results of a calculation performed using the THERMOS code is satisfactory. It is concluded that the 176Lu/Dy set appears to be adequate for the thermal spectrum analysis of light-water-moderated lattices, while the 175Lu/Dy set can provide rather accurate integral data for the epithermal component of the neutron spectrum.