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Fusion Science and Technology
Latest News
Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
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.