ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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.
G. Winkler, Donald L. Smith, James W. Meadows
Nuclear Science and Engineering | Volume 76 | Number 1 | October 1980 | Pages 30-42
Technical Paper | doi.org/10.13182/NSE80-A19290
Articles are hosted by Taylor and Francis Online.
Cross sections for the 63Cu(n,α)60Co reaction have been measured by activation for neutron energies from threshold to 10 MeV relative to well-known 238U fission cross sections. The data obtained are compared with values from the literature and the resulting spectrum-averaged cross sections based on the new results are given for the 235U thermal fission and 252Cf spontaneous fission neutron field. The new results indicate that the long-standing discrepancy between differential and integral data for the reaction 63Cu(n,α)60Co has been eliminated.