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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
A. M. Gadalla and N. A. L. Mansour
Nuclear Science and Engineering | Volume 90 | Number 3 | July 1985 | Pages 320-329
Technical Paper | doi.org/10.13182/NSE85-A17773
Articles are hosted by Taylor and Francis Online.
Equilibrium relationships in the uranium-tungsten-oxygen system have been established as a function of temperature at different oxygen pressures. Isobaric sections in air and oxygen and at oxygen partial pressures of 0.01 and 0.07 were constructed, using the thermobalance. Mixtures of U3O8 and WO3 pick up weight in air, forming UWO6, which exists over a wide range of compositions taking both uranium oxides and WO3 in solid solution. The compound WO3 takes a limited amount of uranium oxide in solid solution and U3O8 also dissolves a limited amount of W03. The miscibility gap between the solid solutions of UWO6-x and U3O8-y on the one hand and the solid solutions of UWO6-x and WO3-z on the other hand decreases by decreasing oxygen partial pressure and/or by increasing temperature. Each group of compatible solutions finally merges into a single phase deficient in oxygen. The two single phases exist over a wide range of compositions and melt over ranges of temperatures depending on the initial composition. Above a critical oxygen partial pressure (between 0.01 and 0.07 atm), solid solutions of UWO6-x and U3O8-y, as well as solid solutions of UWO6-x and WO3-z, melt partially with isothermal oxygen loss. Increasing the oxygen partial pressure increases the melting temperatures and produces eutectic liquids richer in oxygen.