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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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Nuclear Science and Engineering
July 2025
Nuclear Technology
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Latest News
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.
G. L. Wire, J. L. Straalsund
Nuclear Technology | Volume 30 | Number 1 | July 1976 | Pages 71-76
Technical Paper | Material | doi.org/10.13182/NT76-A31625
Articles are hosted by Taylor and Francis Online.
A simple yet powerful method is developed to calculate steady-state creep rates in a nonvolume conservative plastic deformation that is linear in the applied stress. The method is applicable to complex stress distributions that exist in many nuclear reactor core components. Application of the method leads immediately to the steady-state creep rates for bending in plane stress and plane strain for a swelling rate that depends on position only through variation in the hydrostatic stress. The bending rate in plane strain can be significantly lower than the corresponding rate in plane stress. The method accommodates arbitrarily spatially varying stress-free swelling rates with only minor generalization. For example, the steady-state stress distribution induced by non-uniform swelling through a tube wall is obtained simply by application of standard formulas for thermal stresses in this geometry.