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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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J. A. Bonnet, Jr., R. K. Osborn
Nuclear Science and Engineering | Volume 43 | Number 1 | January 1971 | Pages 1-4
Technical Paper | doi.org/10.13182/NSE71-A21240
Articles are hosted by Taylor and Francis Online.
A method for estimating the average void fraction in water-moderated power reactors is presented. The method might be useful to determine departure from normal boiling conditions or nucleate boiling in boiling and pressurized water reactors, respectively. A standing acoustic wave is introduced in the core and the neutron density is measured, squared, time-averaged, and compared with the same quantity without an acoustic wave. The ratio is inversely proportional to the sixth power of the acoustic velocity; and the acoustic velocity depends on the average void fraction in the core. Consequently, this ratio is very sensitive to the average void fraction in the core.
