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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meeting Spotlight
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.
T. C. Gillett, R. S. Denning, J. L. Ridihalgh
Nuclear Technology | Volume 31 | Number 2 | November 1976 | Pages 244-249
Technical Paper | Shielding | doi.org/10.13182/NT76-A31686
Articles are hosted by Taylor and Francis Online.
Techniques have been developed for the shield design computations of facilities for the handling and processing of plutonium. These techniques involve the application of a modified version of the point kernel code QAD. Because this modified point kernel code maintains the three-dimensional flexibility and computational efficiency of other point kernel codes, it is well suited to the performance of production shielding-design calculations. Correction factors were developed to account for some inadequacies of the point kernel approach. The accuracy of the code has been determined by comparing results obtained for typical shield configurations with ANISN results and has been found to be adequate for most shielding problems encountered in facilities of this type. Limited comparison to available experimental data indicates the techniques give reasonably good accuracy. Sources of radiation considered include neutrons and gammas from fission, neutrons from (α, n) interactions with light elements, and low-energy gammas from alpha decay.