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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.
Michael L. Corradini, James P. Blanchard, Carl J. Martin
Nuclear Science and Engineering | Volume 168 | Number 3 | July 2011 | Pages 185-196
Technical Paper | doi.org/10.13182/NSE10-24
Articles are hosted by Taylor and Francis Online.
The occurrence of a steam explosion for advanced light water reactors (LWRs), whether within or below the reactor pressure vessel in the cavity, is analyzed to determine the possible hazard to structures as a result of dynamic explosion pressures. In current LWRs, in-vessel steam explosions have been determined not to pose a risk-significant threat, while ex-vessel explosions are considered in safety analyses. In advanced LWRs, such analyses are important to demonstrate that such structures will maintain their integrity so that core debris coolability is possible. This paper presents an approach to calculate the dynamic pressures from a steam explosion using the TEXAS-V model and evaluate its effects on surrounding structures using ANSYS. Scenarios for advanced LWRs are reviewed, and a severe accident scenario is used as an example to present our methodology. Such evaluation methods should be considered in future safety studies and be verified with direct comparison to data for energetic fuel-coolant interaction, such as those provided from past KROTOS tests or with current experiments in the international SERENA project.