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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.
A. Bujan, B. Tóth, A. Bieliauskas, R. Zeyen, C. Housiadas
Nuclear Technology | Volume 169 | Number 1 | January 2010 | Pages 1-17
Technical Paper | Reactor Safety | doi.org/10.13182/NT10-A9339
Articles are hosted by Taylor and Francis Online.
Phébus FP tests study the phenomenology of severe accidents in water-cooled nuclear reactors. The first test, FPT0, was performed with fuel irradiated for only 1 week; the second test, FPT1, was performed with fairly similar boundary conditions but with irradiated fuel (burnup: 23 GWd/t). The objective of this work is, on the one hand, to summarize the main experimental results of these two tests concerning the behavior and transport of fission products and structural materials in the circuit and, on the other hand, to identify or to confirm any modeling weaknesses in the SOPHAEROS/ASTEC V1 module used for interpreting the experimental results. Besides comparison with available experimental data, the main results of the entire circuit analyses are compared with former SOPHAEROS/ASTEC V0 analyses and, for so-called quasi-separated steam generator tubes, with one- and two-dimensional Eulerian and Lagrangian (particle tracking) models.Concerning the transport of iodine vapor species, it is shown that the results obtained are compatible with passage of nonnegligible amounts of the measured highly volatile iodine through circuit to containment. It is also shown that these results depend heavily on the considered kinetics of Cd release from the bundle.