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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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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Byung-Ho Lee, Yang-Hyun Koo, Dong-Seong Sohn
Nuclear Technology | Volume 127 | Number 2 | August 1999 | Pages 151-159
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT99-A2991
Articles are hosted by Taylor and Francis Online.
A model for rim porosity that takes into account the effect of overpressurization on rim pores is proposed for high-burnup UO2 fuel. It is based on the assumption that all the fission gases produced are retained in rim pores, and the threshold pellet average burnup required for the formation of the rim region is 40 MWd/kg U. In addition, a thermal conductivity correlation is proposed that uses the rim porosity model developed. This correlation for the rim region considers both degradation of thermal conductivity with burnup across the fuel pellet and additional degradation at the pellet rim due to very high porosity. To calculate the temperature profile across the fuel pellet where the rim region is formed, the present correlation for the rim region is combined with the HALDEN, MATPRO, and SIMFUEL correlations for thermal conductivity for the fuel interior region where the rim feature does not exist. Application of the present correlation to the measured HALDEN fuel centerline temperature (Nuclear Energy Agency public database IFA-562) shows that good agreement between the calculated and measured fuel centerline temperature is obtained when the present correlation is combined with HALDEN thermal conductivity. On the other hand, when it is combined with SIMFUEL thermal conductivity, which does not consider the effect on thermal conductivity of fission gases and other volatile fission products, lower centerline temperature is obtained due to the characteristics of the SIMFUEL.