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The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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2024 ANS Annual Conference
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Las Vegas, NV|Mandalay Bay Resort and Casino
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Fusion Science and Technology
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.
P. W. Humrickhouse, J. P. Sharpe, M. L. Corradini
Fusion Science and Technology | Volume 52 | Number 4 | November 2007 | Pages 1022-1026
Technical Paper | Tritium, Safety, and Environment | doi.org/10.13182/FST07-A1629
Articles are hosted by Taylor and Francis Online.
The Toroidal Dust Mobilization eXperiment (TDMX) has been developed to investigate the mobilization of dust in fusion reactor Loss of Vacuum Accident (LOVA) scenarios. TDMX data will be utilized to validate new computational models for dust resuspension and transport in LOVAs. This work describes the modeling of the compressible vessel filling in TDMX using the CFD code Fluent. Results for fast (~0.1 s) pressure transients are found to agree well with experimental and analytical results. Modeling longer transients has thus far been less successful, due primarily to the difficulty in resolving the accompanying small flow passages.