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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.
R. A. Bennett, R. E. Heineman
Nuclear Science and Engineering | Volume 8 | Number 4 | October 1960 | Pages 294-299
Technical Paper | doi.org/10.13182/NSE60-A28859
Articles are hosted by Taylor and Francis Online.
The thermal neutron absorption rate in “1/v” materials has been observed near a discontinuity in the temperature of a graphite moderator. A plausible group diffusion model of the space and energy distributions of the thermal neutrons has been assumed. The experimental data have been used to obtain the transfer cross sections, called rethermalization cross sections, to be used with this model. The cross sections obtained for crystalline graphite are small compared to those expected for gaseous graphite; but they increase by a factor of about seven, from (1.9 ± 0.05) × 10−3 to (14.5 ± 2.6) × 10−3 cm−1, from the lowest temperature of 108°K to the highest temperature of 666°K.