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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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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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.
Katsuhiro Sakai, Satoru Sugawara, Hisashi Hishida, Tetsuo Kobori
Nuclear Science and Engineering | Volume 91 | Number 3 | November 1985 | Pages 262-278
Technical Paper | doi.org/10.13182/NSE85-A17303
Articles are hosted by Taylor and Francis Online.
A method to predict the probabilistic distribution of channel coolant flow rate was developed for a boiling-water-cooled, pressure-tube-type reactor. This method deals with the probabilistic deviation of core flow distribution and total coolant flow rate based on the characteristics of the correlation between two-phase pressure drop of a primary core cooling system and the characteristics of the recirculation pump Q-H. The effect of local and global uncertainties on the probabilistic variation of channel coolant flow rate is discussed in terms of coolant flow correlation among all of the pressure tube channels. The probabilistic deviation of channel coolant flow rate due to uncertainties in fabrication tolerances, experimental data, and physical properties has been evaluated for various operating conditions of the FUGEN reactor. Predicted channel flow deviations were in good agreement with the deviation of actual measured data in the FUGEN reactor.