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Division Spotlight
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.
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.
Christopher J. Blesch, F. A. Kulacki, R. N. Christensen
Nuclear Technology | Volume 59 | Number 1 | October 1982 | Pages 104-118
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A33057
Articles are hosted by Taylor and Francis Online.
Integral methods have been applied to the prediction of the far field thermal impact of a nuclear waste repository. The heat balance integral (HBI) has been applied to a semi-infinite layered domain in which the repository is represented by an infinite plane beneath either one or two sublayers. Calculations for pressurized water reactor spent fuel with an initial thermal loading of 60 kW/acre are carried out for various stratigraphies and overburden compositions. Thermophysical properties of all geologic media are assumed independent of temperature, but thermal conductivities are varied to include upper and lower bounds, as well as generic values. The results demonstrate that thermophysical properties of the overburden have the most important influence on temperature distributions and peak temperature at any position above the repository. Where a comparison to exact or numerical solutions is possible, the HBI predicts maximum temperature increases in the overburden to within 10%. Heat fluxes to the earth’s surface are found to be relatively insensitive to overburden composition. For dome salt, the surface heat flux is 1.2 to 2.7% of the initial thermal loading over 105 yr. This variation corresponds to about a threefold variation in the effective thermal conductivity of the overburden. Similarly, low percentages of thermal loading reach the surface for bedded salt, granite, basalt, or shale. In any case, the present results provide upper bound estimates on both repository temperature and surface heat flux.