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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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Nuclear Science and Engineering
July 2025
Nuclear Technology
Fusion Science and Technology
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.
Mario Dalle Donne, Stefan Dorner
Fusion Science and Technology | Volume 9 | Number 3 | May 1986 | Pages 484-491
Technical Paper | Tritium System | doi.org/10.13182/FST86-A24735
Articles are hosted by Taylor and Francis Online.
The Karlsruhe Nuclear Center is studying the conceptual design of a helium-cooled poloidal ceramic blanket with beryllium multiplier for the Next European Torus. To maintain the tritium losses from the plant below 10 Ci/day, a separate helium purge flow is required. In the case of a high-pressure purge flow, tritium containment requires an oxidizing atmosphere in the purge flow region. The consequences of the resulting T2O partial pressure on Li2O are assessed. A purge flow at 1 bar does not require an oxidizing atmosphere.
