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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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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.
Yuan Chen, Gang Chen, Rong Liu, Haiping Guo, Wenjiang Chen, Wenmian Jiang, Jian Shen
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1919-1924
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-A29622
Articles are hosted by Taylor and Francis Online.
Using the Total Absorption Method, the neutron multiplications in beryllium have been measured. A deionized water sphere with outer radius of 75 cm and a polyethylene sphere with outer radius of 69 cm were used as the total neutron absorbers. Neutron distributions in the spheres were measured using 235U fission chambers. The relative and the efficiency-determined methods were compared. Important sources of experimental errors were detailly analyzed. 4 groups of neutron multiplications in beryllium up to 14.85 cm thick for two total absorbers and two methods of measurement have been obtained and agreement among them is satisfactory. Measured results have been compared with ANISN calculations using data from ENDF/B-IV. It is shown that the differences between calculations and experiments are up to 15%.
