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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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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.
Lung Kwang Pan, Cheng Si Tsao
Nuclear Science and Engineering | Volume 135 | Number 1 | May 2000 | Pages 64-72
Technical Paper | doi.org/10.13182/NSE00-A2125
Articles are hosted by Taylor and Francis Online.
This work verifies the neutron flux for a modified zero-power-reactor facility using neutron activation. Ten foils are activated and counted to illustrate the precise neutron spectrum at a particular location inside the reactor core through the computerized software Spectrum Analysis by Neutron Detector-II (SAND-II). In addition, neutron spectra derived from 11 different locations are compared with the computational results from the WIMS reactor analytical software, respectively, and then the neutron distribution with various energy groups inside the reactor core is rearranged. A quantified index, AT, is also introduced to compare the experimental and computational results. In this work, the ATs are evaluated as 2.28 ± 0.48, which implies a slight discrepancy between the computational and experimental results. Moreover, a softer neutron spectrum evaluated by the WIMS calculation is verified by further examining the experimental data. Recommendations on how to apply the WIMS calculations are also offered.