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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
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.