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GAO report describes cleanup progress at Moab Mill Site
A new report released by the U.S. Government Accountability Office states that the Department of Energy’s Office of Environmental Management (EM) has disposed of more than 16 million tons of radioactive and hazardous waste from the Moab Mill Site. While cleanup continues at the Cold War–era uranium ore processing site in southeastern Utah, a plan for the next phase of groundwater remediation is still needed, according to the GAO.
R. C. Noyes, P. K. Doherty, S. A. Caspersson, N. Hanus, D. W. Stuteville
Nuclear Technology | Volume 26 | Number 4 | August 1975 | Pages 460-471
Technical Paper | Fuel | doi.org/10.13182/NT75-A24446
Articles are hosted by Taylor and Francis Online.
A study to determine the optimum pin diameter for carbide fuel in a liquid-metal fast breeder reactor was made. Several subsidiary parameters, including coolant velocity, burnup, and properties of the clad and subassembly duct material, were studied for their effect on the optimum pin diameter. The materials used in the analysis were Type 316 stainless steel and a high strength, low swelling material capable of operation to a damage fluence of 3.6 × 1023 n/cm2. Using doubling time and fuel cycle cost as the basis for judgment, an optimum pin outer diameter (o.d.) range of 0.37 to 0.40 in. was found for both the near-term and advanced structural materials. Because of practical limits of the Fast Test Reactor testing, an o.d. of 0.37 in. is recommended. The optimum pin diameter was found to be independent of fuel burnup. From a doubling time point of view, no incentive was found for development of carbide fuel with a burnup greater than 80 to 90 MWd/kg.