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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
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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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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.
H. K. Clark
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 164-170
Technical Paper | Analysis | doi.org/10.13182/NT80-A32462
Articles are hosted by Taylor and Francis Online.
Critical masses and subcritical mass limits in oxide-water mixtures were calculated for actinide nuclides other than 233U, 235U, and 239Pu that have an odd number of neutrons in the nucleus; Sn transport theory was used together with cross sections, drawn from the GLASS multigroup library, developed to provide accurate forecasts of actinide production at Savannah River. The subcritical limits are: 201 g for 241Pu, 13 g for 242mAm, 90 g for 243Cm, 30 g for 245Cm, 900 g for 247Cm, 10 g for 249Cf and 5 g for 251 Cf Association of 241Pu with an equal mass of 240Pu increases the 241Pu limit to a value greater than that for pure 239Pu. Association of 242mAm with 241 Am increases the limit for the mixture to that for dry, theoretical density AmO2 at isotopic concentrations of 242mAm less than ∼6%. Association of 245Cm with 244Cm increases the limit according to the formula 30 + 0.3 244Cm/245Cm up to the limit for dry CmO2. A limiting mass of 8.15 kg for plutonium containing at least 67% 238Pu as oxide was calculated that applies (provided 240Pu exceeds 241Pu) with no limit on moderation.