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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
Victor Iannello, Neil E. Todreas
Nuclear Science and Engineering | Volume 101 | Number 4 | April 1989 | Pages 315-329
Technical Paper | doi.org/10.13182/NSE89-A23621
Articles are hosted by Taylor and Francis Online.
Mixed convection flow for parallel vertical channels connected at upper and lower plenums is studied. The one-dimensional conservation equations are formulated in dimensionless form using channel integral parameters. Based on this formulation, expressions are derived for stable flow and reversal of channel flow. The equations are then used to calculate the flow redistribution within a liquid-metal reactor core during natural circulation primary loop flow. A channel/plenum interaction phenomenon, which limits the applicability of using one-dimensional formulations, is modeled, and a correlation is formulated utilizing measured results to predict the onset of this behavior. Finally, the reversal of a heated channel from upflow to downflow, which cannot be predicted with a onedimensional analysis, is described, and the channel/plenum interaction previously modeled is proposed as the mechanism that initiates this flow reversal.