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Accelerator Applications
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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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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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.
Glen R. Edwards, Kent A. Jones, Steven F. Halvorson
Fusion Science and Technology | Volume 10 | Number 2 | September 1986 | Pages 243-252
Technical Paper | Blanket Engineering | doi.org/10.13182/FST86-A24976
Articles are hosted by Taylor and Francis Online.
Recent inertial confinement fusion reactor designs utilize liquid 17Li-83Pb blankets to absorb the neutron and thermal fluxes. One of the crucial concerns of these designs is the compatibility of structural alloys with this lithium-lead alloy, especially because of this liquid's possible propensity for embrittling materials. Current candidate pressure vessel steels for liquid lithium or lithium-lead containment are the Cr-Mo steels such as HT-9 (12 Cr-1 Mo), 2.25 Cr-1 Mo, and niobium-stabilized 2.25 Cr-1 Mo. This investigation was therefore aimed at characterizing the lithium-lead embrittlement susceptibility of the weldments of these steels subjected to a 17Li-83Pb liquid. Results of these embrittlement studies have shown that as-welded heat-affected zones of low phosphorus and sulfur 2.25 Cr-1 Mo, niobium-stabilized 2.25 Cr-1 Mo, and HT-9 steels all exhibit liquid-metal-induced embrittlement susceptibility when subjected to a 17Li-83Pb liquid. The embrittlement, however, was found to be very dependent on post-weld heat treatment. Normally extensive post-weld heat treatments greatly ameliorate the 17Li-83Pb embrittlement, rendering these steels acceptable for 17Li-83Pb containment.