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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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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.
R. Nijsing, W. Eifler
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 289-299
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32329
Articles are hosted by Taylor and Francis Online.
The present version, THARC-S, of the transient thermohydraulic subassembly code, THARC, under development at the Joint Research Centre at Ispra, has been applied to predict the transient thermohydraulic behavior of liquid-metal fast breeder reactor subassemblies subjected to loss-of-flow conditions. Information is given on the present status of development of THARC. Computational results are presented for 217-rod subassemblies, both for grid and wire spacers. It is shown that radial power gradients and overcooling in the region adjacent to the wrapper wall cause boiling inception in the subassembly to be incoherent with, as a consequence, a more gradual boiling and voiding process than expected on the basis of a one-dimensional approach. It is demonstrated that heat capacity effects associated with the fuel rods and the wrapper wall are of considerable importance. Aspects associated with code validation in out-of-pile bundle experiments are also briefly discussed.