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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.
Song Jiangfeng, Huang Guoqiang, Huang Zhiyong, Chen Chang’an, Luo Deli
Fusion Science and Technology | Volume 67 | Number 3 | April 2015 | Pages 576-579
Proceedings of TRITIUM 2013 | doi.org/10.13182/FST14-T83
Articles are hosted by Taylor and Francis Online.
Tritium is a fuel and the most mobile and significant radioactive sources for ITER. In the design of TBM tritium systems of China, the safety design of common chemistry engineering system and tritium safety design are considered at the same time. It is necessary to avoid a continuous increase of the tritium concentration in the coolant and to reduce the tritium permeation into the secondary coolant as well as environment. In this paper, the design and tritium permeation analysis of China HCCB TBM port cell are introduced. At first, the primary design considerations of the system are given to fulfill the engineering demand of the ordinary system (non radioactive system). Then the tritium permeation, the release analysis, the effect of tritium release to the people and environment are discussed. From the calculation of the tritium permeation in the systems housed in the port cell, tritium permeation barrier is needed in the higher temperature components such as the reduction bed and the heater.