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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.
Manfred Sappok, Wolfgang Steinwarz
Nuclear Technology | Volume 125 | Number 3 | March 1999 | Pages 363-370
Technical Note | Reactor Safety | doi.org/10.13182/NT99-A2953
Articles are hosted by Taylor and Francis Online.
In the framework of European research activities on nuclear safety, experimental work on ex-vessel core melt behavior under prototypical conditions is being performed. Spreading on various material surfaces and verification of relevant computer codes are the main tasks of the COMAS project, leading to an improvement of the design basis for corium retention systems. In particular, the large-scale two-dimensional spreading test [1:6 with respect to the European pressurized water reactor (EPR) spreading area] shows a quick and uniform melt distribution even for thin melt layers supporting the EPR corium stabilization concept.
