ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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.
Douglas W. Stamps
Nuclear Science and Engineering | Volume 157 | Number 3 | November 2007 | Pages 331-343
Technical Paper | doi.org/10.13182/NSE07-A2731
Articles are hosted by Taylor and Francis Online.
A general analytical model was developed to predict the thermal-hydraulic behavior in box-type catalytic recombiners of different sizes and configurations. The fluid mechanics of the recombiner was modeled as flow through a chimney, which resulted in a modified form of the classic chimney equation to predict the exit gas velocity and flow rate. The thermal behavior of the recombiner was modeled using the transient form of the energy equation for reacting flow. The model was assessed using data from recombiners developed by the NIS Ingenieurgesellschaft Company (NIS), Siemans, and Atomic Energy of Canada Limited. Good agreement was obtained between the model and experimental data for the time-dependent hydrogen concentration in the test facility and the capacity of the recombiner in terms of the hydrogen recombination rate, both key parameters in the analyses of accidents in nuclear power plants. The analytical model could be reduced to the form of an empirical correlation developed for the NIS recombiner under simplifying conditions.