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Comparative Cost Study of Processing Stainless Steel-Jacketed UO2 Fuel: Mechanical Shear-Leach vs Sulfex-Core Dissolution
Comparison of the economics of mechanical shear-leach and Sulfex decladding-core dissolution head end treatments for processing typical tubular bundles of stainless steel-jacketed UO2 nuclear fuels.
Distribution of Uranium at Low Acid : Low Uranium Concentrations into 4-1/2 Percent TBP-AMSCO
Report wherein acid free uranyl nitrate hexahydrate was distributed into 4-1/2 percent TBP-Amsco 125-90W and combined with various concentrations of acid in order to study the distribution of uranium and hydrolysis effects.
Effect of Explosive Impacting on Uranium
Abstract: The tensile and yield strengths of both cast and wrought uranium discs were substantially increased by explosively impacting them at room temperature and at 375 deg F. However, the room-temperature impacting caused gross damage in the cast material and slight internal damage in the wrought material at the highest impacting pressures. Impacting at 375 deg F, which is just above the brittle-ductile transition temperature for uranium, was the most effective method for increasing the strengths with no damage to either the cast or wrought material. This impacted material retained some of its increased strength after a low temperature (425 deg C) vacuum anneal that greatly increased the elongation. A salt anneal caused a partial recrystallization in the impacted cast uranium. (auth).
Engineering Test Reactor Critical Facility Control System Manual
This report consists of the description, drawings, connections, and schematics of the various control elements that make up the control system of the Engineering Test Reactor Critical Facility (ETRC).
Evaluation of Radiation Stabilizers for Terphenyl by High-Temperature Electron Irradiation
From summary: "Experiments to determine effectiveness of additives to reduce radiolytic damage to a mixture of isometric terphenyls in which 93 separate compounds were evaluated."
Fire Test of Wooden-Jacket Shield for Radioisotope Shipping Container
"This report covers fire tests conducted on an experimental design of a wooden-jacket shield for radioisotope shipping containers" (p. i).
Gas-Cooled Reactor Project Semiannual Progress Report: March 1963
Report documenting the design and testing progress of the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
IBM 1401 Computer Produced and Maintained Library Circulation Records
Report issued by the University of California Lawrence Radiation Laboratory discussing a method of updating library circulation records on an IBM 1401 computer. The report describes the methods of generating and updating the records using transaction cards to create computer tapes that are sorted and updated to prepare current reports of circulation information.
In Vivo Gamma Counting Method of Determining Uranium Lung Burden in Humans
Scintillation spectrometry is used to measure the gamma activity from uranium for determining lung burden in the human body.
Results of ATR Sample Fuel Plate Irradiation Experiment
From abstract: "Fuel materials proposed for use in the Advanced Test Reactor were evaluated."
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