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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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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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.
R. Venkataraman, R. F. Fleming, E. D. McGarry
Nuclear Science and Engineering | Volume 126 | Number 3 | July 1997 | Pages 314-323
Technical Paper | doi.org/10.13182/NSE97-A24483
Articles are hosted by Taylor and Francis Online.
A new measurement-based method has been developed to determine the photofission contribution to measured responses of fission reactions in a mixed radiation field of neutrons and photons. Using this method, reliable upper and lower bounds can be established for the photofission contributions. Knowledge of the photon energy spectrum and the photofission cross sections is not required. The method involves the measurement and calculation of spectral indices of a fission reaction relative to a reaction whose response does not include any photon contribution. The differential changes in the spectral indices are measured as well as calculated with and without a gamma-ray attenuator. The measurements include responses from both neutrons and photons, whereas the calculations include contributions from neutrons only. An equation is derived for the ratio of photofission rate to neutron-induced fission rate using the definitions of the spectral indices. From this equation, algebraic upper and lower bounds can be determined for the photofission contribution using a minimum and a maximum value for the mass attenuation coefficient of the gamma-attenuating material at all photon energies. The method was tested in the radiation field inside the Materials Dosimetry Reference Facility (MDRF), which is a National Institute of Standards and Technology reference neutron field operating at the Ford Nuclear Reactor at the University of Michigan. Established algebraic upper bounds for the photofission contributions to the 237Np and 238U fission reactions in the MDRF were found to overlap zero. Conservative statistical upper bounds were established at the la level of confidence, and these are 0.87% for the 237Np fission reaction and 0.55 % for the 238U fission reaction.