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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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.
R. T. Jacobs, J. A. Merrill
Nuclear Science and Engineering | Volume 8 | Number 6 | December 1960 | Pages 480-496
Technical Paper | doi.org/10.13182/NSE60-A25834
Articles are hosted by Taylor and Francis Online.
The comparative correlations of this report thoroughly demonstrate that significantly more precise equations for calculating burnout heat flux can be obtained by following the proposed “system-describing” concept, that if the independent, system-describing variables of a system are known, the burnout heat flux can be predicted. With this concept, the independent variable of inlet temperature has been used rather than the dependent variable of outlet subcooling or enthalpy. The same statistical (regression analysis) method of correlation was used for burnout data from several sources with both inlet temperature and outlet enthalpy so that the consistently better predictions using inlet temperature would not be attributed to using a different method of correlation. Due to the fact that Reactor technology and design no longer allow the engineer safety factor added upon safety factor, a decided advantage of the regression analysis correlation is that it is possible to calculate the statistical uncertainty of the predicted burnout heat flux.