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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.
D. T. Goldman, F. D. Federighi
Nuclear Science and Engineering | Volume 16 | Number 2 | June 1963 | Pages 165-175
Technical Paper | doi.org/10.13182/NSE63-A26496
Articles are hosted by Taylor and Francis Online.
A model is proposed for calculating the scattering of thermal energy neutrons by polyethylene. It is seen that a reasonable fit to the experimental total cross section results. This model is then used to calculate infinite medium spectra and the results compared with calculations using water and perfect gas scattering kernels, with a harder predicted spectrum apparent. The results are compared with experimental data for two amounts of absorption, and agreement between experiment and theory using an appropriate scattering model is observed. The model is then used to calculate reactor quantities for a particular one-dimensional finite lattice. The sensitivity of the flux spectra and criticality to the choice of scattering kernel is presented. The former quantity is more sensitively dependent than the latter.