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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.
T. J. Carter
Nuclear Technology | Volume 45 | Number 2 | September 1979 | Pages 166-176
Technical Paper | Material | doi.org/10.13182/NT79-A32307
Articles are hosted by Taylor and Francis Online.
In the quest to reduce cladding strain from power ramps and thereby reduce the incidence of defects, various aspects of pellet geometry have been examined. The influence of pellet end squareness was investigated in steady-power irradiation of UO2 with end tapers well in excess of the currently allowable deviation from end squareness, and no increase in postirradiation cladding strains was noticeable. Five ramp tests were performed to examine the effects of pellet length-to-diameter ratio, the width of the loadbearing annulus (shoulder) at the dished end, and the effect of adding a small 45-deg edge chamfer. Although cladding strains were significantly reduced by changes in pellet geometry, there appears little incentive to do so from the viewpoint of preventing Zircaloy cracking, since defects occurred in rods that had lower overall strains than those that survived.