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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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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.
M. A. Abdou, C. W. Maynard
Nuclear Science and Engineering | Volume 56 | Number 4 | April 1975 | Pages 360-380
Technical Paper | doi.org/10.13182/NSE75-A26683
Articles are hosted by Taylor and Francis Online.
Methods are investigated for calculating nuclear heating and dose due to the interaction of nuclear radiation with matter. A theoretical model is developed for calculating neutron fluence-to-kerma factors (kerma = kinetic energy released in materials) from basic nuclear data. No major simplifying assumptions are introduced, and the accuracy of the calculated fluence-to-kerma factors depends only on the availability and accuracy of the basic nuclear data. Based on this theoretical model, a computer program called MACK was written to calculate fluence-to-kerma factors from nuclear data in ENDF format. An algorithm for investigating the validity of the kerma factors by using an integral energy balance was also developed. The validity of the theoretical model and the correctness of the computation of the kerma factors obtained in the present work were verified through the use of this algorithm. Comparison of these kerma-factor results with previous work showed that they provide a considerable improvement in kerma-factor and nuclear-heating calculations. It is also shown that there is currently some inconsistency in preserving the energy between the basic neutron interaction data and the gamma-ray production data. It is suggested that the photon-production matrix be processed simultaneously with the neutron kerma factors to ensure consistency.