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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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 Science and Engineering
June 2025
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.
Haiying Liang, Zhendong Wu, Zhengjun Zhang, Yinlu Han, Xuesheng Jiao
Nuclear Science and Engineering | Volume 187 | Number 2 | August 2017 | Pages 107-126
Technical Paper | doi.org/10.1080/00295639.2017.1295699
Articles are hosted by Taylor and Francis Online.
All cross sections, angular distributions, energy spectra, and double differential cross sections are consistently calculated and analyzed for n+93Nb reaction at incident neutron energy up to 200 MeV based on the nuclear theoretical models. The theoretical calculated results are compared with the existing experimental data and the evaluated data in ENDF/B-VII, JENDL-4, and TENDL-2015. The calculated results agree with the experiential data.