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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.
Mien-Win Wu, Jen-Chang Chou
Nuclear Science and Engineering | Volume 63 | Number 3 | July 1977 | Pages 268-275
Technical Paper | doi.org/10.13182/NSE77-A27039
Articles are hosted by Taylor and Francis Online.
The cross section of the 58Ni(n, p)58Co reaction was determined by the activation method for neutron energies from 3 to 4.8 MeV. Neutron fluxes were measured with a laboratory-fabricated proton recoil telescope consisting of a radiator, an evacuated cell, and a surface barrier detector. The absolute efficiencies of the telescope for different neutron energies have been interpreted by Monte Carlo calculation as well as by a direct integration method. The fraction of activations induced by neutrons following single elastic scattering to those without scattering in the nickel sample was also calculated by a Monte Carlo program. The neutron attenuation through the nickel sample was also considered. Major sources of error in the cross-section determination are summarized and discussed. The total error was estimated to be 4 to 5%.