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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
Michael B. Stanka, James M. Adams, Charles M. Eisenhauer
Nuclear Science and Engineering | Volume 134 | Number 1 | January 2000 | Pages 68-76
Technical Paper | doi.org/10.13182/NSE00-A2100
Articles are hosted by Taylor and Francis Online.
Proton recoil measurements of the 252Cf fission neutron leakage spectrum from a 50-cm-diam iron sphere are performed as a means of checking the degree to which the ENDF/B-VI iron inelastic scattering cross section resolves the well-known discrepancy between predicted and observed neutron transport. These measurements were performed at the National Institute of Standards and Technology using a rotating proton-recoil spectrometer over an energy range of 50 keV to 4.5 MeV. In addition, Monte Carlo neutron transport calculations were performed of the iron-moderated neutron spectrum generated in the experiment. Below 1 MeV, the spectral measurements are in good agreement with a corresponding calculation for the iron-moderated neutron leakage spectrum obtained using the ENDF/B-VI cross-section library. However, the calculation continues to underpredict the neutron fluence above 1 MeV by as much as 11%, which is greater than the average statistical uncertainty of the measured data. Finally, the measurements are compared with those obtained from a similar set of experiments made by two different laboratories in the Czech Republic. The results compare favorably with both of these measurements and indicate the best agreement with the Monte Carlo transport calculations with respect to the integral neutron fluence.