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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
June 16–19, 2024
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.
K. R. Schultz, A. R. Veca, G. A. Deis, P. Y. S. Hsu, R. E. Nygren, H. Herman
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 763-768
Blanket and First Wall Engineering | doi.org/10.13182/FST83-A22952
Articles are hosted by Taylor and Francis Online.
The First Wall/Blanket/Shield (FWBS) Program has the goal to provide the development and testing of FWBS systems for magnetic fusion reactors. Program Element II of this program is to develop the thermal-hydraulic and thermomechanical data base for blanket and shield components. The critical blanket/shield data needs were identified, alternate techniques to simulate fusion neutron bulk heating were evaluated, and a detailed technical plan was developed. The initial focus is on the critical issues of solid breeder blankets. Two single effect scoping tests are currently in progress to determine the heat transfer characteristics and thermomechanical stability of the solid breeder bed. The design of an integral test to simulate all the non-nuclear aspects of the blanket has been completed. Preliminary planning for a fission reactor-based nuclear test has also been done. Future testing will investigate alternate solid breeder blanket materials and configurations and will begin the investigation of the critical MHD effects of liquid metal blanket concepts.