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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.
Armando B. Antoniazzi, Clive S. Morton, Kevin P. Chen, Baojun Liu
Fusion Science and Technology | Volume 54 | Number 2 | August 2008 | Pages 635-638
Technical Paper | Process Applications | doi.org/10.13182/FST08-A1895
Articles are hosted by Taylor and Francis Online.
A tritium exposure apparatus has been designed and built for the purposes of generating a high-pressure tritium atmosphere at 523 K. The loading system consists of a uranium tritide storage bed, an intermediate tritium transfer chamber filled with 5A molecular sieve, and the sample exposure chamber. The loading system resides in a sealed glovebox with a nitrogen atmosphere that is continually purged through a Glovebox Clean-up System. The tritium used in each loading experiment is approximately 6000 Ci (22 TBq). The process entails transferring the tritium inventory from the uranium storage bed to the cryogenically cooled (77 K) molecular sieve chamber. The molecular sieve at liquid nitrogen temperature is capable of adsorbing tritium to densities of 290 Ci/gram at one atmosphere. At 523 K a maximum tritium pressure of 21 MPa is achieved. The loading apparatus is used to develop high-density radioactive isotope fuel for self-powered microelectronic and micromechanical devices. This paper presents the design specifics of the tritium exposure apparatus, the steps taken in generating the high-temperature, high-pressure tritium atmosphere and the performance characteristics of the apparatus. Additionally, the handling practices and equipment utilized to conduct the tests safely are presented.
