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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.
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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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Latest News
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
Philippe Planquart, Chiara Spaccapaniccia, Giacomo Alessi, Sophia Buckingham (von Karman Inst), Katrien Van Tichelen (SCK-CEN)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 131-142
The thermal-hydraulics challenges of a nuclear reactor are numerous and mastering these is crucial for the design and safety of new reactors. Numerical simulation through computational fluid dynamics (CFD) codes or System Thermal-Hydraulics (STH) codes can address a lot of the different questions, nevertheless the use of water modeling for the study of the thermal-hydraulic behavior of a new primary system and the validation of codes remains an extremely valuable tool. A water model of the pool-type PbBi-cooled MYRRHA reactor has been developed at the von Karman Institute in collaboration with SCK•CEN. It is a full Plexiglas model at a geometrical scale 1/5 of MYRRHA. This transparent water model allows the application of optical measurement techniques, like Particle Image velocimetry (PIV) for the flow characterization. Local results of PIV measurements performed in the lower plenum at the entrance of the core are presented and compared with CFD results for a nominal operating condition and a natural convection case simulating the decay heat removal. A very good agreement has been found in the velocity field. The results also show the importance of the radial flow entering the core of the water model in natural convection.