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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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.
Emil Beták, Ewa Droste, Stefan Mikolajewski, Wojciech Ratynski, Edward Rurarz, Tadeusz Kempisty, Subramanian Raman
Nuclear Science and Engineering | Volume 132 | Number 3 | July 1999 | Pages 295-307
Technical Paper | doi.org/10.13182/NSE99-A2064
Articles are hosted by Taylor and Francis Online.
Using 14.7-MeV neutrons and gamma-ray spectroscopy with high-purity germanium detectors, the activation cross sections have been measured for the following nuclear reactions: (a) 44Ca(n,p)44K, = (39 ± 4) mb; (b) 44Ca(n,np)43K, = (3.0 ± 0.3) mb; (c) 44Ca(n,)41Ar, = (31 ± 3) mb; (d) 42Ca(n,p)42K, = (138 ± 12) mb; (e) 43Ca(n,p)43K, = (90 ± 9) mb; and (f) 48Ca(n,2n)47Ca, = (613 ± 60) mb. A 98.6% enriched 44Ca target was used for reactions (a), (b), and (c) and a natural calcium target for reactions (d), (e), and (f). These cross sections have been compared with some earlier published experimental values and with some results of calculations. The latter include those based on semiempirical formulas and those given by the preequilibrium plus compound-nucleus code GNASH. When applied to reactions (a), (d), (e), and (f), this code gives cross-section values that are consistently above the measured values.