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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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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.
P. M. Prajapati, Bhawna Pandey, C. V. S. Rao, S. Jakhar, T. K. Basu, B. K. Nayak, S. V. Suryanarayana, A. Saxena
Fusion Science and Technology | Volume 66 | Number 3 | November 2014 | Pages 426-431
Technical Paper | doi.org/10.13182/FST14-804
Articles are hosted by Taylor and Francis Online.
The current state of nuclear data evaluations requires improvement for fusion applications. In this context, the excitation function of the 56Fe(n,α)53Cr reaction from threshold to 20 MeV has been calculated using the Hauser-Feshbach statistical model with preequilibrium effects by the TALYS-1.4 code. Different types of nuclear level density models have been used in the calculation. The present calculations are compared with existing experimental data as well as with latest available evaluated nuclear data libraries ENDF/B-VII.1, JEFF-3.2, and JENDL-4.0. Good agreement between the calculated and the experimental data validates the nuclear model approaches with increased predictive power to supplement and extend the nuclear database. The present calculations have also been compared with the (n,α) reaction cross-section systematics at 14.5-MeV neutron energy.