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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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.
J. Ligou
Nuclear Science and Engineering | Volume 11 | Number 1 | September 1961 | Pages 26-38
Technical Paper | doi.org/10.13182/NSE61-A25980
Articles are hosted by Taylor and Francis Online.
This paper describes an extension of the method of Nordheim-Scalettar to the case of rods partially inserted in a bare reactor. In this study, the axial flux harmonics are introduced. It is assumed that the extrapolation distances of the rods for thermal neutrons still have the same value whatever their insertion length may be. This extrapolation distance can be calculated especially from data relative to rods of infinite length. Calculation methods for the determination of the efficiency of rod assemblies and the distribution of thermal neutron flux are described. It should be noted that the determination of the flux distribution may require the use of many more harmonics than the determination of rod efficiency, since the results converge more rapidly in the latter case. Significant examples are given. The calculation method has been programmed to be used with a BULL Gamma AET Computer.