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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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.
G. P. Sabol, S. G. McDonald
Nuclear Science and Engineering | Volume 63 | Number 1 | May 1977 | Pages 83-90
Technical Paper | doi.org/10.13182/NSE77-A27007
Articles are hosted by Taylor and Francis Online.
Alloying additions of 0.5 and 1.0 wt% niobium, respectively, have been added to Zircaloy-4 in an attempt to improve its high-temperature corrosion resistance. Ingots of these modified alloys were fabricated to a 0.76-mm-thick sheet via a processing sequence compatible with commercial tubing production and were given one of four different final anneals. Subsequent testing indicated that the niobium additions had little or no effect on corrosion resistance in 360°C water. In 427°C steam, however, the 0.5%-niobium addition provided increased resistance to spalling, while the 1.0%-niobium addition decreased both cumulative weight gains and post-transition corrosion rates. The weight gains exhibited by the 0.5%-niobium alloy were relatively insensitive to final heat treatment, whereas the 1.0%-niobium alloy suffered a degradation in properties as the extent of the final anneal increased. These trends in corrosion performance were subsequently correlated with the second-phase particle size distributions present in the alloys, the best performance being obtained when the mean particle diameter was <400 to 500 Å. It was concluded that both niobium additions improved the corrosion performance of Zircaloy-4 at elevated temperatures, but that the best performance was obtained at the 1.0-wt%-niobium level.