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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.
M. S. Pandey, J. B. Garg
Nuclear Science and Engineering | Volume 60 | Number 4 | August 1976 | Pages 399-404
Technical Paper | doi.org/10.13182/NSE76-A26901
Articles are hosted by Taylor and Francis Online.
High resolution measurements of the total neutron cross section from 200 eV to ∼50 keV in natural copper have been performed using time-of-flight techniques. From the R-matrix analysis of the data, values of E0, Γn, Jπ of resonances, strength functions, and average level spacings are obtained. For in units of eV−1/2 were obtained. Similarly, the average level spacings are determined for 63Cu⟨D⟩ J = 1 = (2.38 ± 0.38) keV, ⟨D⟩J = 2 = (3.57 ± 0.70) keV and for 65Cu⟨D⟩J = 1 = (3.85 ± 0.88) keV and ⟨D⟩J = 2 = (5.0 ± 1.2) keV.
