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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
Ian H. Hutchinson, Steve F. Horne, Gerasimos Tinios, Stephen M. Wolfe, Robert S. Granetz
Fusion Science and Technology | Volume 30 | Number 2 | November 1996 | Pages 137-150
Technical Paper | Special Section: Plasma Control Issues for Tokamaks / Plasma Engineering | doi.org/10.13182/FST96-A30746
Articles are hosted by Taylor and Francis Online.
A general approach to plasma shape control and its application to the Alcator C-Mod tokamak are described. The method is linear in the magnetic measurements but is entirely algorithmic, requiring no fitting of databases. Estimators of the shape parameters are based on a complete vacuum reconstruction of the flux, so that control points can be defined anywhere within the reconstructed region. The conversion of flux differences into flux-surface distances and the calculation of appropriate coil currents for controlling each parameter require a specific reference equilibrium. However, the control is very insensitive to the choice of reference equilibrium provided that the shape parameters are chosen appropriately. Control current combinations that are orthogonal, in the sense of changing one parameter and not the others, are obtained. Experiments with these estimators and controllers show them to be accurate and robust over a wide range of plasma shapes.