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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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
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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.
J. T. Mihalczo
Nuclear Science and Engineering | Volume 56 | Number 3 | March 1975 | Pages 271-290
Technical Paper | doi.org/10.13182/NSE75-3
Articles are hosted by Taylor and Francis Online.
The spatial distribution of the neutron importance in bare and natural-uranium-reflected uranium (∼93.2 wt% 235U) and plutonium (∼4.7 at % 240Pu) metal spheres was measured using 252Cf neutron sources. The spatial distribution of the fission density from activation measurements in the bare spheres and those previously measured for the reflected spheres are presented.Comparison of these distributions with those from S16 transport theory calculations showed that the measured and calculated results agreed very well for the bare spheres and in the central core of the reflected spheres. The disagreement in the natural uranium reflector increased with radius and attained values as large as ∼35% at the outer surface. The sensitivity of the calculations to the cross sections is examined.These measurements were undertaken to properly account for spatial effects in the point reactor kinetics description of Rossi-α measurements. The spatial-effects factors obtained from these measurements, which multiply the correlated amplitude of the Rossi-α measurement, were 1.123, 1.109, 1.163, and 1.214 for the bare uranium, bare plutonium, reflected uranium, and reflected plutonium spheres, respectively. The error in these values is ± 0.010.