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Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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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Fusion Science and Technology
Latest News
ARPA-E announces $40 million to develop transmutation technologies for UNF
The Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E) announced $40 million in funding to develop cutting-edge technologies to enable the transmutation of used nuclear fuel into less-radioactive substances. According to ARPA-E, the new initiative addresses one of the agency’s core goals as outlined by Congress: to provide transformative solutions to improve the management, cleanup, and disposal of radioactive waste and spent nuclear fuel.
W. Fundamenski
Fusion Science and Technology | Volume 53 | Number 4 | May 2008 | Pages 1023-1063
Technical Paper | Special Issue on Joint European Torus (jet) | doi.org/10.13182/FST08-A1746
Articles are hosted by Taylor and Francis Online.
The tokamak plasma boundary, which is typically identified with the area of open field lines known as the scrape-off layer (SOL), determines the degree of plasma-wall interaction. SOL physics, much of which is concerned with the exhaust (removal) of particles and energy from the plasma, has been one of the major topics investigated on JET during the past two decades. In this chapter, SOL transport/exhaust studies on JET are reviewed. The discussion proceeds chronologically, beginning with the limiter SOL and treating in turn the successive divertors (Mk0, MkI, MkIIA, and MkIIGB) with which JET was equipped in subsequent years. When appropriate, old results are reinterpreted in the light of recent improvements in our understanding of edge/SOL turbulence and edge-localized modes (ELMs). Although emphasis is placed on deuterium transport in the SOL, impurity transport is briefly considered. In particular, the effect of divertor closure, of L-mode versus H-mode, and of inter-ELM versus ELM erosion on plasma purity (Zeff), radiation (frad), and confinement (E) is briefly discussed. The chapter concludes with a summary of empirical scaling expressions for SOL profile widths (radial e-folding lengths) in both limiter and divertor configurations.