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The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2024 ANS Annual Conference
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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.
Alessandro Dodaro, Franco Vittorio Frazzoli, Romolo Remetti
Nuclear Technology | Volume 144 | Number 1 | October 2003 | Pages 130-140
Technical Paper | Radiation Measurements and Instrumentation | doi.org/10.13182/NT03-A3433
Articles are hosted by Taylor and Francis Online.
The "angular scanning" method allows both localization of hot spot(s) and the evaluation of the corresponding activity. Taking into account the experimental setup parameters (e.g., drum geometry, drum-detector distance, collimator geometry, etc.), the peak count rate versus the angular displacement is modeled as a theoretical analytical function of three independent variables (unknowns) for each hot spot: the two coordinates of the hot-spot center of mass and the corresponding activity value. Solutions for unknowns are obtained from equating, for each angular displacement, the experimental count rate to the corresponding theoretical one. Such a procedure has been applied to the SRWGA gamma scanner of the Casaccia Research Center utilizing a set of Waste Packages Reference Standards (with different matrices) where the gamma sources in different radial-azimuthal positions can be located.
