ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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.
M. V. Gregory, H. C. Honeck
Nuclear Science and Engineering | Volume 61 | Number 3 | November 1976 | Pages 437-445
Technical Note | doi.org/10.13182/NSE76-A26932
Articles are hosted by Taylor and Francis Online.
Control algorithms for power-shaping calculations and critical rod bank position searches are described. The algorithms allow a flux computation module using a finite difference solution of the few-group neutron diffusion equations with coarse-mesh rebalancing to be directly extended to control calculations. The control algorithms are formulated as an extension of the standard critical buckling search by recasting the procedure for calculating the eigenvalue. A comparison of the power-shaping calculation with an equivalent keff calculation demonstrates that the former requires approximately the same number of outer iterations as the latter.