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Radiation Protection & Shielding
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
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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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.
Brandon Distler, Steve Baker, Jordan Gladden (Transware Enterprises), Hatice Akkurt (EPRI)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 925-930
Cask Loader, an EPRI software system is a relational database program that facilitates the automated selection of candidate spent fuel assemblies for placement into dry cask storage canisters from spent fuel pools. Cask Loader allows users to compute the decay heat values for an extended burnup range using a modified regulatory guidance approach. Due to increased efficiency in operation, the number of assemblies with higher burnups increased exponentially within the past two decades. The NRC Regulatory Guide 3.54, published in 1999, set applicability limits for burnup that are below the current operational experience. Subsequently, within the past decade, the need for extending the burnup ranges significantly increased. Only two measurement points are available for extended burnup range. Analyses were performed for these two points and extended by including additional typical and hypothetical PWR and BWR assemblies. For this study, decay heat values were computed using Cask Loader and ORIGEN and were then compared against each other. The computational results showed that compared to ORIGEN, Cask Loader overestimates the decay heat values without any exception and therefore can be considered conservative in its estimation of decay heat values for high burnup range. In this paper, the comparative decay heat values are presented.