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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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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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, Vijay K. Dhir
Nuclear Technology | Volume 100 | Number 3 | December 1992 | Pages 331-346
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34729
Articles are hosted by Taylor and Francis Online.
Flooding of the reactor vessel cavity 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 vessel lower head containing molten core material is numerically investigated using a two-dimensional implicit finite difference scheme. Results are obtained for the vessel shell temperature, pool temperature, and crust thicknesses for both unsteady and steady-state conditions. For both cases, the thermal behavior of the vessel lower head is investigated by parametrically changing the emissivity of the pool surface, the vessel wall, and the upper structure and by changing the temperature of the upper structure. For a certain set of parameters, nucleate boiling on the outer surface of the vessel wall is effective in lowering the temperature of the inner wall of the vessel below the melting temperature of steel. Steady-state results are obtained by using two different heat transfer correlations for the natural convection in the molten pool, which helps in understanding how uncertainties in the modeling of physical processes can influence the evaluation of accident management strategies.