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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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2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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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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Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
M. Lipa, J. Schlosser, F. Escourbiac
Fusion Science and Technology | Volume 56 | Number 3 | October 2009 | Pages 1124-1149
Technical Papers | Tore Supra Special Issue | doi.org/10.13182/FST09-A9171
Articles are hosted by Taylor and Francis Online.
To fulfill the Tore Supra mission (the realization and study of high-performance long-duration discharges), the development of reliable actively cooled plasma-facing components is mandatory. This was foreseen from the beginning of Tore Supra, and since 1985, the Tore Supra team has been involved in the development and fabrication of actively cooled plasma-facing components. The initial configuration of the machine in 1988 included a 12 m2 inner first wall made of stainless steel tubes armoured with brazed graphite, outer water-cooled stainless steel panels, and modular pump limiters. This configuration, using the inner wall as limiter, allowed 20- to 30-s-duration plasma discharges to be performed. Further progress required the development of a more reliable brazing technique and a limiter support system mechanically independent of the vacuum vessel. A new configuration (Composants Internes et Limiteur project), using a completely new concept of high-heat-flux components (including notably a braze-free bond between carbon-fiber composite tiles and copper heat sink), was therefore launched in 1997. With this new configuration, discharges up to 6 min with 1 GJ of injected and removed power were achieved in 2003.