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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 Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Fusion Science and Technology
February 2024
Latest News
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?
R. J. La Haye
Fusion Science and Technology | Volume 29 | Number 1 | January 1996 | Pages 126-133
Technical Paper | Divertor System | doi.org/10.13182/FST96-A30662
Articles are hosted by Taylor and Francis Online.
Nonaxisymmetric error fields arising from departures of the coil systems from axisymmetry can pose serious problems for the tokamak divertor. The X points of the divertor are particularly sensitive to being shifted by n ≠ 0 error fields; toroidal “bundle diverting” or bunching of heat flux coming from the core of the tokamak can produce hot spots on carefully designed divertor structures. Toroidal variation of the angle of incidence on the divertor by the n ≠ 0 error field can also locally peak the heat flux. Multiple field line tracing of a typical diverted Tokamak Physics Experiment (TPX) configuration with nonconcentric poloidal field (PF) coils is used to predict that if the toroidal variation of the peak divertor heat flux is to be kept to within ±25%, the principal PF coils responsible for the diverting must be aligned to ±2 mm of concentricity with the toroidal field.