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2024 ANS Annual Conference
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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.
Akio Sagara, Nobuyoshi Ohyabu, Osamu Motojima
Fusion Science and Technology | Volume 27 | Number 3 | April 1995 | Pages 532-535
Plasma Particle and Heat Control Studies | doi.org/10.13182/FST95-A11962957
Articles are hosted by Taylor and Francis Online.
A new method of high efficient discharge cleaning using Local Island Divertor(LID) in the Large Helical Device(LHD) project is proposed as one of optional merits of LID. This method drastically shortens the discharge cleaning time required in wall conditioning to remove main impurities such as oxygen on the surface of plasma facing components. The first estimation concludes very fast conditioning in less than one hour even in a large machine like LHD, which usually needs more than a few weeks with conventional discharge cleaning methods. Demonstration in actual plasma devices is proposed.
