ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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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July 2025
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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.
Gerhard Karsten
Nuclear Technology | Volume 77 | Number 3 | June 1987 | Pages 349-353
Technical Note | Material | doi.org/10.13182/NT87-A33975
Articles are hosted by Taylor and Francis Online.
The application of image-analytical, indenting, and quantitative scanning electron microscopic methods on irradiated uranium and mixed-oxide fuel materials yields nonlinear thermodynamic operational data. Any oxide fuel material from a specific fabrication process undergoes its own means of transformation toward thermodynamic equilibrium through structural metamorphoses by irreversible processes far from equilibrium. The related dissipation energies vary with burnup and temperature because of the variable capability of energy storage, due to specific structural reactions on nuclear impacts. This fact leads to a large variety of operational material properties. Preferable operational hyperelasticity and subsequent viscoelasticity can be predetermined by intentional selected kinetic processing during fuel fabrication.