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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.
M. Coquerelle, C. T. Walker
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 43-53
Technical Paper | Fuel | doi.org/10.13182/NT80-A32446
Articles are hosted by Taylor and Francis Online.
Mixed carbide, carbonitride, and nitride fuels have been irradiated in DFR and Rapsodie to a maximum burnup of 7.8 at.% at a maximum linear power of 135 kW·m−1. At low burnup, xenon release from helium-bonded fuels was found to be dependent on the chemical composition of the fuel Release was greatest from carbide (75%) and least from nitride fuels (35%). At medium burnup, improved gap conductance led to a fall in the fuel centerline temperature and consequently a decrease in gas release. For nitride and carbonitride fuels, over 75% of the retained fission gas was contained in bubbles (<1 µm in diameter) and in the fuel matrix. For all three fuels, xenon release from the outer unrestructured region of the fuel was <15%, whereas release from the central porous region was 50% or more. In the restructured region, gas was released to the plenum by way of interconnected pores. Gas in pores contained proportionally more krypton than the bonded gas, and consequently, it is proposed that atomic diffusion is the principal mechanism of gas transport within the fuel.
