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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.
Meeting Spotlight
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.
Andrea Rizzolo, Piero Agostinetti, Mauro Breda, Moreno Maniero, Diego Marcuzzi, Modesto Moressa, Matteo Valente
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 164-170
Blanket Materials Technology | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14130
Articles are hosted by Taylor and Francis Online.
The ITER Neutral Beam Test Facility (PRIMA - Padova Research on ITER Megavolt Accelerator) is planned to be built at Consorzio RFX (Padova, Italy). PRIMA includes two experimental devices: a full-size plasma source with low voltage extraction called SPIDER (Source for Production of Ions of Deuterium Extracted from RF plasma) and a full-size neutral beam injector at full beam power called MITICA (Megavolt ITER Injector Concept Advancement).The beam source components are exposed to high and focused heat loads during beam production, and they are actively cooled, being at high voltage, by ultrapure water, which flows through cooling channels machined inside the components. The high power loads, the complexity of the cooling circuits, and their small, rectangular cross sections are design critical issues.The results of the tests carried out on the single cooling channel prototypes (SCPs) for the SPIDER accelerator grids and their performances in terms of pressure drop and heat exchange calculation are presented. The SCPs have been tested in environmental conditions similar to injector ones, i.e., they have been subjected to thermal loads up to the average heat power density of 1 MW/m2 , in a vacuum environment (0.5 Pa). The experimental results have been cross-checked with computational fluid dynamics analyses and analytical models.