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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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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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Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
R. Maingi, J. Gilligan, O. Hankins, L. Owen, P. Mioduszewski, T. Uckan
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1778-1782
Impurity Control and Plasma-Facing Component | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29600
Articles are hosted by Taylor and Francis Online.
A critical issue in long-pulse tokamak discharges is the need for density control and power-handling capability in the presence of wall outgassing, neutral beam injection, and pellet fueling. Direct particle and energy exhaust in Tore Supra is obtained with a system of pump limiters, including six located at the bottom of the machine and a large horizontal module at the outer midplane. This paper focuses on two-dimensional (2-D) modelling of the scrape-off-layer (SOL) and outboard pump limiter, using the MHD fluid code b2 and the neutral transport code DEGAS. Temperature, density, and ion flux data from Langmuir probes in the throat of the limiter are used along with estimates of the power scrape-off-length from infrared camera data to obtain a self-consistent description of the SOL plasma/neutral source distribution within the limiter and throughout the SOL. Good agreement with measured quantities is obtained, and three to four iterations of the b2/DEGAS calculation are necessary for convergence.