ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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.
E. Smith
Nuclear Technology | Volume 50 | Number 2 | September 1980 | Pages 187-189
Technical Note | Fuel | doi.org/10.13182/NT80-A32545
Articles are hosted by Taylor and Francis Online.
As a result of a post-irradiation metallographic study of power-ramped Canadian natural uranium, heavy-water-moderated and -cooled power (CANDU) reactor fuel rods, it was recently concluded that the observed beneficial effects of graphite CANLUB coating on CANDU fuel’s tolerance to power-ramp defects stem primarily from the interaction of the coating with fission products, rather than by lubrication of the fuel-cladding interface. These arguments are based on a consideration of fuel cracking patterns and the assumption that stress corrosion crack growth within the cladding is the controlling event in the failure process. While these arguments are examined in detail, the present reappraisal leads to the same view of the primary origin of the beneficial effects of graphite coatings on CANDU fuel rod performance.
