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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.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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.
James T. Cronin, Kord S. Smith
Nuclear Technology | Volume 100 | Number 2 | November 1992 | Pages 174-183
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34740
Articles are hosted by Taylor and Francis Online.
A methodology for homogenization and functionalization of one-dimensional cross sections for RETRAN has been developed and encoded into the SIMULATES and SLICK computer programs. The method relies on the SIMULATE-3 nodal reactor analysis code to provide accurate solutions of the three-dimensional neutron diffusion equation in two energy groups. The process of producing the required data involves two distinct problems: (a) the spatial homogenization of the three-dimensional cross sections and diffusion coefficients into one-dimensional variables and (b) the functionalization of the one-dimensional data in terms of the feedback variables of coolant density, fuel temperature, and control fraction. The homogenization method is based on equivalence theory and preserves the eigenvalue and one-dimensional planar reaction rates of the three-dimensional solution. The functionalization of the homogenized cross sections is accomplished by performing analogous one-dimensional state calculations with the RETRAN thermal-hydraulic models and then fitting to the RETRAN feedback variables. The methodology has been verified by comparing the results of one-dimensional calculations performed with the one-dimensional cross sections to three-dimensional calculations. Close agreement between the one- and three-dimensional results has been demonstrated.