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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.
Sven Bader, Ashley Spry (AREVA Federal Services, LLC)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 647-652
A methodology is described that allows for the direct comparison of many diverse objectives with an end result of a rank-ordered evaluation of options that reflects the decision makers' preferences. This methodology, the multi-attribute utility analysis (MUA), is utilized to establish a ranking of routes and associated modes of transport (e.g., truck, rail, barge) to move used/spent nuclear fuel (UNF/SNF) from independent spent fuel storage installations (ISFSIs) to a Class I carrier. Preliminary evaluations have been performed to identify viable modes of transport from some ISFSIs where the only remaining vestige of the reactor site is the ISFSI and hence, very little transportation infrastructure remains at these “stranded” sites for performing these shipments. The MUA is a structured methodology designed to handle the trade-offs among multiple objectives (i.e., attributes) and provides a transparent, rational, and defensible analysis that is easy to explain and communicate and has been used for decades to provide logically consistent analyses of options (i.e., modes and routes) that are intended to achieve more than one objective, where no single option dominates the others on all of those objectives. The ultimate result from the MUA is a list(s) of the most to the least favored/preferred routes from the ISFSI. This paper provides an overview of the MUA methodology and provides examples of its application to several ISFSIs with shutdown reactors.