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Division Spotlight
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.
Meeting Spotlight
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.
H. Kaikkonen, J.-P. Salo, P. Silvennoinen
Nuclear Technology | Volume 38 | Number 2 | April 1978 | Pages 312-320
Technical Paper | Low-Temperature Nuclear Heat / Reactor | doi.org/10.13182/NT78-A32029
Articles are hosted by Taylor and Francis Online.
Optimization of the back-end services of the fuel cycle is solved by linear programming. A mathematical model governs the flow of fissile material from the reactor to spent fuel storages, to reprocessing and/or ultimate disposal, and to the fabrication of mixed-oxide fuel. The computer program developed is amenable to the optimization of the overall material flow together with recycle schedules and capacities under the prevailing market conditions and their trends. The income tax consideration is not included in the analysis, and therefore the results are applicable mainly to government-owned power production. Using the nuclear program of Finland, calculations are made to study the break-even reprocessing costs with regard to the throwaway costs. According to our conservative price estimates, the recycle benefit amounts to some 6.4 to 6.9% as calculated from the total discounted fuel cost over the years from 1977 to 2004. Over the time period of a few years at the beginning of the plutonium recycle, the levelized costs would be lower in the throwaway case, which is contrary to the overall result.