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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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High-temperature plumbing and advanced reactors
The use of nuclear fission power and its role in impacting climate change is hotly debated. Fission advocates argue that short-term solutions would involve the rapid deployment of Gen III+ nuclear reactors, like Vogtle-3 and -4, while long-term climate change impact would rely on the creation and implementation of Gen IV reactors, “inherently safe” reactors that use passive laws of physics and chemistry rather than active controls such as valves and pumps to operate safely. While Gen IV reactors vary in many ways, one thing unites nearly all of them: the use of exotic, high-temperature coolants. These fluids, like molten salts and liquid metals, can enable reactor engineers to design much safer nuclear reactors—ultimately because the boiling point of each fluid is extremely high. Fluids that remain liquid over large temperature ranges can provide good heat transfer through many demanding conditions, all with minimal pressurization. Although the most apparent use for these fluids is advanced fission power, they have the potential to be applied to other power generation sources such as fusion, thermal storage, solar, or high-temperature process heat.1–3
Mohamed S. El-Genk, Timothy M. Schriener, Ragai Altamimi, Andrew Hahn
Nuclear Science and Engineering | Volume 197 | Number 12 | December 2023 | Pages 3082-3109
Regular Research Article | doi.org/10.1080/00295639.2023.2190723
Articles are hosted by Taylor and Francis Online.
The Extended Length Test Article–Cartridge Lead is a test assembly for conducting in-pile research in the Versatile Test Reactor to support the advanced molten lead–cooled reactor under development at the Westinghouse Company. This work investigates four pumping options for circulating molten lead at 500°C and develops an integrated thermal-hydraulic model to estimate the demand curves. The four pumping options fit within cartridge riser tubes that are 57.0 and 68.8 mm in diameter. These options are (1) gas lift pumping, (2) the miniature submerged annular linear induction pump, (3) the miniature submerged direct-current electromagnetic pump, and (4) the miniature axial-centrifugal flow mechanical pump. Gas lift pumping is the simplest and is fully passive with no heat dissipation, but it generates the lowest pumping pressure and flow rate. The mechanical pump and direct-current electromagnetic pump generate the highest pumping pressures, flow rates, and average velocities of molten Pb in the test article of three-fuel rodlets in a triangular lattice. The mechanical pump designs provide the highest flow velocities in the test article and the slowest decrease in pumping pressure with increased flow rate at low thermal power dissipation. The optimized electromagnetic pump designs with no moving parts and elevated temperature ALNICO-5 permanent magnets meet or exceed the target flow velocities in the test article but at higher rate of heat dissipation than the mechanical pump designs.