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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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Latest News
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.
Bertram Wolfe
Nuclear Science and Engineering | Volume 13 | Number 2 | June 1962 | Pages 80-90
Technical Paper | doi.org/10.13182/NSE62-A26137
Articles are hosted by Taylor and Francis Online.
Expressions for the reactivity effects produced by the motion of a fluid in a reactor core are developed using perturbation techniques. It is shown that in a fixed fuel reactor significant reactivity effects can be produced by the “drag” of the fluid on the neutron population. In a fluid fuel reactor, the transport of the delayed neutron precursors can produce reactivity changes approaching a dollar for very moderate fluid velocities. An expression for the delayed neutron lifetime in a fluid fuel reactor is developed, and the corresponding inhour equation is derived.