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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.
James A. Davis
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 127-146
Technical Paper | doi.org/10.13182/NSE68-A18015
Articles are hosted by Taylor and Francis Online.
By using variational means, it is found for any one velocity system with non- zero absorption cross section having either vacuum, reflecting, or antireflecting boundary conditions that the transport solution is, in a very specific sense, approached monotonically from above by the solutions to the odd PN equations and from below by the solutions to the even PN equations, provided the PN solutions are obtained by using appropriate continuity and external boundary conditions. That is to say, odd and even PN calculations “bracket” the transport solution. In one instance, the escape probability is bounded and, in another, the disadvantage factor. This theoretical result, along with certain numerical evidence, suggests that the modified P2 approximation of Dawson may serve as a practical, reasonably accurate alternative to diffusion theory for certain realistic design problems.