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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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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.
F. W. Staub, N. Zuber, G. Bijwaard
Nuclear Science and Engineering | Volume 30 | Number 2 | November 1967 | Pages 279-295
Technical Paper | doi.org/10.13182/NSE67-A17338
Articles are hosted by Taylor and Francis Online.
Experimental data are presented on the transient response of the vapor volumetric concentration in a boiling liquid. The experiments were conducted with Refrigerant-22 in forced upward flow through an electrically heated circular tube. The experiments were performed by oscillating the power input to the metal test section while maintaining a constant discharge pressure and a constant inlet liquid velocity. The amplitude of the power oscillations was varied between 5 and 40% of the average power at frequencies between 0.01 and 10 cps. Steady-state and transient void fractions were measured at six axial locations using a two-beam x-ray attenuation traverse method. Satisfactory agreement is shown between the results predicted by the void propagation equation and the experimental data. It is shown in particular that: 1) The rate of propagation of the voids as well as the wave form of the void disturbance as it propagates along the cluct can be predicted by means of kinematic waves 2) The void response depends upon the flow regime 3) Both the propagation velocity and the wave form can be predicted rather accurately if the effects of flow regime are taken into account. The loss of accuracy, introduced by not considering the effect of flow regime, is also demonstrated.