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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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.
Francis H. Lewis, Patrick D. Soran
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 116-125
Technical Note | doi.org/10.13182/NSE78-A27277
Articles are hosted by Taylor and Francis Online.
Monte Carlo neutron transport calculations of critical radii of bare UH3 spheres as a function of 233U and 235U enrichment in 238U were carried out using three different calculational methods: 1. the continuous-energy 2. method the multigroup approximation 3. the probability table method. Also calculated were the average neutron removal lifetimes and median fission-producing neutron energies for these critical systems. Results of these calculations were analyzed and compared to quantify and bound self-shielding effects arising from the neutron cross-section resonances in calculating these moderated critical assemblies. Although the critical radii of these assemblies are sensitive to the resonances in 238U, the removal lifetime seems to be affected much more by the fissile isotope resonances. The probability table method gives results that are in excellent agreement with continuous-energy calculations, thereby eliminating the need for special cross-section processing for each separate enrichment when using multigroup cross sections.