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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
K. Behringer, G. Kosály, Lj. Kostić
Nuclear Science and Engineering | Volume 63 | Number 3 | July 1977 | Pages 306-318
Technical Paper | doi.org/10.13182/NSE77-A27042
Articles are hosted by Taylor and Francis Online.
In view of recent experimental work, the neutron noise in a boiling water reactor is believed to be separable into local and global components. It is the existence of the local component that makes possible the measurement of steam velocity by correlating the signals of axially placed in-core neutron detectors. In the present paper, we use a one-dimensional (axial) model of the core and solve the two-group diffusion equations satisfied by the neutron noise. The solution is shown to be composed of two terms that can be identified as the theoretical counterparts of the components found in experiments. The properties of the two terms are discussed in the special case of an axially propagating disturbance of the moderator density (steam content).