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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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Nuclear Science and Engineering
October 2024
Nuclear Technology
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August 2024
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.
Timothy D. Welch, August W. Cronenberg
Nuclear Science and Engineering | Volume 67 | Number 2 | August 1978 | Pages 263-269
Technical Note | doi.org/10.13182/NSE78-A15444
Articles are hosted by Taylor and Francis Online.
An important question to the liquid-metal fast breeder reactor safety program is a description of molten fuel dynamics, or, more specifically, whether fuel will freeze locally on structural material within the reactor core, preventing dispersal and nuclear shutdown, or in the extremeties of the fuel assembly. In this Note, a comparison is made between the solidification processes for single-component (i.e., UO2) and mixed-oxide fuel [i.e., (U, Pu)O2] by solving a Stefan-type problem for both pure and binary alloy solidification. Analytic calculations indicate that the freezing rate of the mixed fuel is not significantly different from that for the single-component system; thus, single-front analysis may be used for such mixed-oxide fuels in assessing safety questions associated with solidifacation phenomena.