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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.
Meeting Spotlight
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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Latest News
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.
Terry A. Ring, Byung Sang Choi, J. Paulo Perez, Brian Van Devener, Randy C. Polson, Douglas Crawford, Dennis Keiser, Daniel Wachs
Nuclear Technology | Volume 205 | Number 6 | June 2019 | Pages 801-818
Technical Paper | doi.org/10.1080/00295450.2018.1542252
Articles are hosted by Taylor and Francis Online.
Scanning electron microscopy, transmission electron microscopy, and X-ray photoelectron spectroscopy have been used to characterize the surface of depleted uranium molybdenum (DU-Mo) alloys as a chemical surrogate to determine potential challenges with the surfaces of manufactured and stored U-Mo foils and powders. Even when stored and shipped in an inert atmosphere, U-Mo has a tenacious surface contamination of oxygen and carbon. The 8 at. % molybdenum (DU-8Mo) powder and 10 at. % molybdenum (DU-10Mo) foil samples have surface contamination of oxygen and carbon in different ratios that is hundreds to thousands of nanometers thick. The DU-8Mo powder sample has been stored in an inert atmosphere and as a result has a lower carbon-to-oxygen ratio at the surface than the DU-10Mo foil sample that was stored in air. This surface contamination has not been removed by up to 20 min of argon ion sputtering nor with 5% hydrogen in argon heat treatment for up to 96 h at 950°C.