ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
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
Standards Program
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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May 2025
Latest News
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.
Leonard W. Gray
Nuclear Technology | Volume 52 | Number 1 | January 1981 | Pages 66-72
Technical Paper | Chemical Processing | doi.org/10.13182/NT81-A32690
Articles are hosted by Taylor and Francis Online.
Plutonium metal dissolves readily in sulfamic acid; the dissolution rate is a function of surface area, sulfamic acid concentration, and temperature. Below a temperature of ∼ 50°C, the dissolution mechanism appears to proceed through a PuH2 intermediate that yields a pyrophoric sludge. Above a temperature of ∼60°C, neither the intermediate nor the sludge forms unless the sulfamic acid concentration drops below 0.4 M. Overall dissolution rates of 400 to 500 g Pu/h are obtainable with typical plutonium buttons. Downstream processing requires conversion of the sulfamate to a nitrate medium. Approximately 90% of the residual sulfamate ion can be precipitated as sulfamic acid by the addition of two volumes of 72% HNO3 to one volume of the plutonium sulfamate-sulfamic acid solution if the solution is chilled to -10°C. The small amount of sulfamate remaining can be oxidized either by diluting the nitric acid to ∼3 M and irradiating the solution with ultraviolet light or by diluting the solution with pre-irradiated 3 M HNO3.