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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
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.
Taiki Muneoka, S. Fukada, R. Yoshimura, K. Katayama, Y. Edao, T. Hayashi
Fusion Science and Technology | Volume 68 | Number 2 | September 2015 | Pages 443-447
Technical Note | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-903
Articles are hosted by Taylor and Francis Online.
Development of an efficient tritium recovery method is indispensable in order to compose a liquid blanket system of a D-T fusion reactor in the near future. Here, tritium recovery using a bubbling tower is focused on, and the behavior of H transfer between fluidized lithium-lead (Li-Pb) and gas bubbles of Ar-H2 or pure Ar is examined analytically and experimentally under isothermal conditions. Gas of Ar-H2 or pure Ar is injected into fluidized Li-Pb through an I-shape nozzle made from SS-316. Time variations of the H2 concentration in gas bubbles that come out from fluidized Li-Pb are measured by gas chromatography. Mass-transfer coefficients to correlate rates of H atom transfer between Li-Pb and gas bubbles are obtained by fitting analytical equations to experimental results. The solution is derived under conditions where H transfer between bubbles and liquid Li-Pb is limited by diffusion in the Li-Pb boundary layer. The parameters such as bubble diameter and terminal rising velocity which are used in order to derive analytic formula are estimated from balance among several forces such as gravity, surface tension, inertia force and so on. The behavior of hydrogen transfer at gas-liquid interfaces in liquid blanket is investigated in terms of the mass-transfer coefficient obtained under various conditions.