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Division Spotlight
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.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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. J. McInerney
Nuclear Science and Engineering | Volume 19 | Number 4 | August 1964 | Pages 458-460
Technical Paper | doi.org/10.13182/NSE64-A19004
Articles are hosted by Taylor and Francis Online.
Some exact expressions for the diffusion length are found by using the set of eigenfunctions recently derived for the monoenergetic neutron transport equation. The results are not restricted to any specific degree of anisotropy and are valid for an arbitrary amount of absorption in the medium. A closed-form solution is found for the roots of the familiar equation
