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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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.
Hyunjae Park, V. K. Dhir, William E. Kastenberg
Nuclear Technology | Volume 108 | Number 2 | November 1994 | Pages 266-282
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A35034
Articles are hosted by Taylor and Francis Online.
Flooding of the drywell of a boiling water reactor (BWR) is one of many accident management strategies being proposed to manage severe accidents in light water reactors. The effect of external cooling on the thermal behavior of the BWR vessel lower head containing molten core material has been numerically investigated using a two-dimensional implicit finite difference scheme. Results have been obtained for the vessel shell temperature, the molten pool temperature, and the crust thickness for steady-state conditions. For each equilibrium state, the thermal behavior of the vessel lower head has been investigated by parametrically changing the emissivity of the pool free surface, the vessel wall, the baffle plate, the core shroud, and the upper structure; and the temperature of the upper structure. For a certain set of parameters, nucleate boiling on the outer surface of the vessel wall is found to be effective in lowering the temperature of the inner wall of the vessel below the melting temperature of the steel. For most cases, failure of the BWR baffle plate would occur.