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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.
João Moreira, John C. Lee
Nuclear Science and Engineering | Volume 98 | Number 3 | March 1988 | Pages 244-254
Technical Paper | doi.org/10.13182/NSE88-A22325
Articles are hosted by Taylor and Francis Online.
Control rod worth measurements through the inverse kinetics equation depend on accurate determination of the amplitude function from detector signals. The modal-local method introduced in a previous study estimates space-time changes in the flux or shape function so that the amplitude function can be determined accurately and efficiently. A simple thermal-hydraulic feedback model is included in the modal-local method for at-power reactivity analysis. The method is tested with two simulated rod worth measurements: a zero-power rod drop experiment and a differential rod worth measurement in a power reactor. The modal-local method reproduces the reactivity obtained with the FX2-TH time-dependent diffusion theory code with an overall accuracy of 1 to 2%, except for simulated detectors located in the immediate vicinity of the rod motion.
