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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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.
Jacques Devooght
Nuclear Science and Engineering | Volume 11 | Number 1 | September 1961 | Pages 7-18
Technical Paper | doi.org/10.13182/NSE61-A25978
Articles are hosted by Taylor and Francis Online.
The problem of space dependent thermalization of neutrons is solved for a slab lattice of heavy moderator and fuel. Fuel slabs are replaced by negative plane sources whose strength is computed by transport-theoretical arguments. The Fourier space-transform of the spectrum is obtained by iteration of an integral equation and the solution correct to the order O(Δ2mod) is shown to reduce, in the absence of fuel, to the one found by Hurwitz et al. The influence of the hardening of the spectrum incident on the fuel slab is studied by means of the thermal utilization factor.