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Defense used fuel recycling project advances to partner selection phase
The quest of the Department of Energy’s Office of Environmental Management to find a private-sector partner to design, build, and operate a commercial-scale facility to recycle defense-related used fuel at Idaho National Laboratory has transitioned to the review and selection phase, the DOE said July 7. Responses to a request for applications were due on June 19.
J. C. Wang, Gary L. Jensen, J. B. Czirr
Nuclear Science and Engineering | Volume 113 | Number 1 | January 1993 | Pages 77-85
Technical Paper | doi.org/10.13182/NSE93-A23995
Articles are hosted by Taylor and Francis Online.
Rigorous tests of the Monte Carlo transport code MCNP have been performed by measuring the efficiency of a 6Li-glass moderating neutron detector using Lucite as the moderator relative to the efficiency of the detector using mineral oil as the moderator, and comparing this with the MCNP predicted value. The tests were done using both 252Cf fission-source neutrons and 1.2-MeV neutrons produced by a Van de Graaff accelerator.