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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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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.
Eugene D. Clayton, Hugh K. Clark, Gordon Walker, Richard A. Libby
Nuclear Technology | Volume 75 | Number 2 | November 1986 | Pages 225-229
Technical Note | Criticality Safety | doi.org/10.13182/NT86-A33866
Articles are hosted by Taylor and Francis Online.
Subcommittee 8 of the Standards Committee of the American Nuclear Society is revising the Standard for Nuclear Criticality Control and Safety of Homogeneous Plutonium-Uranium Fuel Mixtures Outside Reactors to include limits on heterogeneous systems. In connection with this effort, a number of criticality calculations were completed for mixed-oxide (PuO2 + UO2) fuel pins in water. The concentration of PuO2 in the UO2 (natural uranium) covered the range from 3.0 to 34 wt%. The isotopic makeup of the plutonium was also varied, up to 25 wt% 240Pu and 15 wt% 241Pu. A search was made on fuel pin diameters and water-to-fuel volume ratios to obtain minimum critical dimensions and masses for a given fuel composition. Calculations made independently by several different members of the Work Group are compiled and compared, together with the proposed subcritical control limits for the Standard. Some difficulties were encountered with calculations pertaining to 30% PuO2 at 240Pu concentrations at water-to-fuel volume ratios and fuel pin diameters outside the area covered by any critical experiment. For this reason, dimensional limits on heterogeneous systems are not being proposed at this time for the Standard with 30% PuO2 at a 240Pu content of 25%. In general, for a given fuel composition of mixed oxides, a heterogeneous arrangement of fuel pins of optimum diameter in water results in substantially smaller minimum critical dimensions than are obtainable for an aqueous homogeneous plutonium-uranium fuel mixture.