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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
Framatome signs contracts with Sizewell C
French nuclear developer Framatome is slated to deliver key equipment for Sizewell C Ltd.’s two large reactors planned for the United Kingdom’s Suffolk coast.
The agreement, reportedly worth multiple billions of euros, was announced this week and will involve Framatome from the design phase until commissioning. The company also agreed to a long-term fuel supply deal. Framatome is 80.5 percent owned by France’s EDF and 19.5 percent owned by Mitsubishi Heavy Industries.
Min Ho Lee (UNIST), Dong-Wook Jerng (Chung-Ang Univ), In Cheol Bang (UNIST)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 20-25
Reactor vessel auxiliary cooling system (RVACS) has been developed to make diverse safety system for sodium-cooled fast reactor (SFR). In the loss of flow (LOF) accident condition, decay heat from the core is transferred to the reactor vessel by natural circulation inside of the sodium pool. The reactor vessel transfers its heat to the containment vessel by the conduction and radiation through the gap between the reactor vessel and the containment. Finally, the containment vessel releases its heat to the air flow from the atmosphere, which is the ultimate heat sink, by means of the RVACS. Although natural circulation of sodium is an important phenomenon because it determines the sodium boiling, it has not been sufficiently researched for the case of the RVACS. Therefore, in this study, natural circulation of the sodium in the LOF condition was analyzed experimentally to evaluate the maximum sodium temperature in the LOF. Water was used as a simulant for the sodium with the reduced scale. The experimental apparatus was scaled down about 1/25 by length, focusing on the modified Boussinesq number which represents the ratio of heat transfer by the natural circulation to the conduction. Because the modified Boussinesq number was the same with that of the actual reactor, overall temperature distribution in scale-downed apparatus with water would be similar to that of the sodium pool. Difference between the maximum and the minimum temperature of the water pool in the experiment was about 0.7oC, which corresponds to 5.1oC temperature difference of the sodium in LOF condition of an actual reactor with the operation of the RVACS. By comparing temperature difference