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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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.
D. P. Jordan G. Leppert
Nuclear Science and Engineering | Volume 5 | Number 6 | June 1959 | Pages 349-359
Technical Paper | doi.org/10.13182/NSE59-A25610
Articles are hosted by Taylor and Francis Online.
Experimental measurements are reported for nucleate boiling of various saturated liquid polyphenyls which are of interest as nuclear reactor coolants. Heat flux is presented as a function of the difference between the heater surface temperature and saturation temperature, and correlations by various semitheoretical methods are discussed. A peak heat flux is reported for all but one of the liquids tested, and good agreement is found with previous work with similar fluids. Methods are suggested which may be used to estimate the nucleate boiling characteristics of these liquids during forced convection at elevated pressures and liquid subcooling, even though the present tests include only pool boiling studies. These methods may be used in feasibility analyses of boiling-polyphenyl cooled and moderated reactors.