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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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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
P. Platania, C. Sozzi
Fusion Science and Technology | Volume 53 | Number 1 | January 2008 | Pages 77-87
Technical Paper | Special Issue on Electron Cyclotron Wave Physics, Technology, and Applications - Part 2 | doi.org/10.13182/FST08-A1655
Articles are hosted by Taylor and Francis Online.
Electron cyclotron resonance heating (ECRH) and electron cyclotron current drive systems in fusion-grade devices meet the severe requirements (in terms of high power handling capability, extended steering range, and room availability) that guide the design of complex multiple-mirror quasi-optical launchers. A valuable step in this process is a beam-pattern calculation in vacuum including relevant electromagnetic effects not easily included in analytical evaluations. In fact, the analytical approach is a means to study the design layout at a first order and is able to derive the relevant quantities as a function of the steering angle and of the beam path in a form suitable to interface with most of the currently available beam-tracing codes. On the other hand, electromagnetic calculations using physical optics tools provide a complete description of the resulting full beam pattern, including the effects of aberration, beam truncation, thermal deformation of the mirrors, and the surrounding structures. Moreover, numerical calculation with reliable and benchmarked codes is a very efficient way to test subsequent updates of a given launcher model, once the basic geometry has been implemented. In this paper, we discuss in particular the application of the GRASP® code to the case of the remote steering option for the ITER ECRH upper launcher.