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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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Nuclear Technology
Fusion Science and Technology
May 2025
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. Maekawa, S. Yamaguchia, C. Konno, Y. Oyama, Y. Ikeda, K. Sekiyamab, K. Kosako
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1949-1954
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29627
Articles are hosted by Taylor and Francis Online.
An integral experiment was performed on a Be cylindrical assembly of 630mm in diameter and 456mm in thick. Measured items were reaction rates, in-system neutron spectra and gamma-ray heating rates. The experimental analysis was performed by the MCNP and DOT3.5 codes using the nuclear data of JENDL-3, JENDL-3PR1, ENDF/B-IV and LANL. For high threshold reactions and integral flux above 10MeV, the calculation based on JENDL-3 agrees well with the experiment, while the calculations of ENDF/B-IV and LANL underestimetes those compared to the experiment. For integral neutron flux of 0.16∼0.5 MeV, the calculation of JENDL-3 agrees well with the experiment. But in the case of ENDF/B-IV the underestimation is 20%. It can be concluded that the nuclear data of Be in JENDL-3 improves very much in accuracy from the temporary version JENDL-3PR1.
