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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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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.
Christophe Poussin, Alain Holcblat
Nuclear Technology | Volume 112 | Number 1 | October 1995 | Pages 108-121
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A15856
Articles are hosted by Taylor and Francis Online.
Thermal stratification may be responsible for the development of severe cracks in the feedwater line of steam generators in pressurized water reactors, leading Framatome to carry out an experimental program especially dedicated to this problem. This developmental program analyzes the mechanisms and the driving parameters of thermal stratification. It develops and qualifies an antistratification device to prevent thermal stratification at the steam generator feedwater nozzle location. The program also compares on-site measurements with mockup results. The outcome of the experimental program is a qualified helical antistratification device to be installed in the thermal sleeve of the steam generator feedwater nozzle. As required, this device significantly reduces thermal stratification effects in the feedwater system, even in very low feedwater flow conditions.
