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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.
J. P. Foster, A. Boltax
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 181-188
Technical Paper | Material | doi.org/10.13182/NT80-A32421
Articles are hosted by Taylor and Francis Online.
Large swelling values associated with a gradual temperature reduction during irradiation have been observed for pressurized tubes irradiated at two initial irradiation temperatures. A comparison of the pressurized tube data with WSA-4 fuel pin cladding swelling data shows that the same behavior is observed in fuel pins subject to temperature changes during irradiation. The fuel pin data cover a large temperature interval, and this information was used to determine temperature and fluence dependencies of the observed enhanced swelling effect. The results show that the enhanced swelling with temperature reductions depends on the initial irradiation temperature, with the maximum value occurring at ∼500°C. The data indicate that the effect saturates with fluence.