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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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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.
D. C. Donovan, D. R. Boris, G. L. Kulcinski, J. F. Santarius
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 507-511
Experimental Facilities and Nonelectric Applications | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-22
Articles are hosted by Taylor and Francis Online.
The University of Wisconsin-Madison Inertial Electrostatic Confinement (IEC) Fusion Research Group has been performing experiments on an IEC device known as HOMER. This device is a 65cm high, 91cm diameter cylindrical aluminum vacuum chamber that contains two concentric spherical wire grids, the outer grid acting as the anode and the inner grid as the cathode. The potential difference between the anode and cathode drives ions towards the center of the grids. Using this device, steady-state D-D fusion reactions are created in order to produce 2.45 MeV neutrons. With the goal of achieving maximum neutron production rates, the following parameters have been varied: cathode voltage, ion current, operating pressure, and the separation distance between the anode and cathode. The studies on pressure, voltage, and current have led to the discovery of trends that allow for the extrapolation of neutron rates at various conditions. The cathode/anode separation studies have offered valuable insight into how the distance between the electrodes effects the concentration of deuterium molecular ions and the ion energy spectra, and has led to the implementation of a configuration that better maximizes neutron production rates.