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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.
S. N. Cramer, E. M. Oblow
Nuclear Science and Engineering | Volume 58 | Number 1 | September 1975 | Pages 33-53
Technical Paper | doi.org/10.13182/NSE75-A26765
Articles are hosted by Taylor and Francis Online.
The results of two integral experiments on carbon, performed at the Oak Ridge National Laboratory (ORNL) and at Intelcom Radiation Technology were compared with Monte Carlo calculations to test evaluated carbon neutron and gamma-ray production data sets. In both experiments NE-213 detectors were used to measure the angular dependence of neutron scattering and gamma-ray production from thick (1-mfp) carbon samples in the energy range from 0.5 to 20 MeV. Additional measurements from the ORNL experiment also provided angular-dependent energy distributions of the scattered neutrons. Multigroup Monte Carlo calculations modeling the two experimental arrangements were made to compare with the measured data. Both ENDF/B-III and ENDF/B-IV carbon data were used in the computations. The results indicate that such experiments are adequate for testing processed neutron scattering and gamma-ray production data (both integral and double differential) to within 10 to 20% over a wide range of incident neutron energies (1 to 15 MeV). Also, on the whole, calculations with the carbon ENDF/B-IV data compared favorably with the measured results over the energy range, tested. The only notable exceptions were the disagreements in the neutron result comparisons above 9 MeV, which were attributed for the most part to errors in the evaluated C(n, n’)3α and elastic angular distribution cross sections in this range.