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Fusion Science and Technology
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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.
André L. Rogister
Fusion Science and Technology | Volume 37 | Number 2 | March 2000 | Pages 271-286
Instabilities and Transport | doi.org/10.13182/FST00-A11963222
Articles are hosted by Taylor and Francis Online.
The phenomenology of transport in magnetically confined plasmas is briefly described and the basic physical concepts underlying the theories of both anomalous and neoclassical transport are reviewed. Anomalous transport is a consequence of supra-thermal electric and magnetic fluctuations driven unstable by various mechanisms. The excited modes saturate by inducing a relaxation of the profiles towards the marginally stable state and via nonlinear coupling of the various modes. Specific theoretical models are described, together with their successes and drawbacks in the light of observed characteristics of plasma confinement. An estimate of the nuclear heating power required to balance the anomalous losses in the International Tokamak Experimental Reactor (ITER) is obtained on the basis of the electrostatic drift wave instability model. Large-scale gyrokinetic turbulence simulations and various “theoretical” transport models are discussed. Recent improvements of neoclassical theory, required in the vicinity of transport barriers, are described.