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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Molten salt research is focus of ANS local section presentation
The American Nuclear Society’s Chicago–Great Lakes Local Section hosted a presentation on February 27 on developments at the molten salt research reactor at Abilene Christian University’s Nuclear Energy Experimental Testing (NEXT) Lab.
A recording of the presentation is available on the ANS website.
Helmut Kunze
Nuclear Science and Engineering | Volume 15 | Number 1 | January 1963 | Pages 1-12
Technical Paper | doi.org/10.13182/NSE63-A26258
Articles are hosted by Taylor and Francis Online.
An analytical method is developed for determining the energy dependent neutron flux in homogeneous and heterogeneous media. Using the heavy gas model scattering operator, neutron spectra in two-dimensional rod reactors of various types are calculated in the diffusion approximation. They show a strong spatial dependence even in the epithermal region, which fact is neglected in the numerical treatment of the problem by Honeck and Kaplan. It is just this epithermal part of the spectrum, which mainly influences the values of the thermal utilization and the η-factor. The value obtained for the latter quantity is too large if the correct neutron spectra in moderator and fuel are replaced by Maxwellian distributions at moderator-temperature or a suitably displaced temperature, for example.