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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Latest News
Constellation seeks rezone for property adjacent to Illinois plant
While no development details have been released, Constellation is asking to rezone 658.8 acres of land it owns around the Byron nuclear plant in Illinois for possible long-term use.
Ji-Hwan Hwang (Chung-Ang Univ), Min Ho Lee, In Cheol Bang (UNIST), Dong-Wook Jerng (Chung-Ang Univ)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 650-656
A concept of the ERVC (External Reactor Vessel Cooling) can be applied to the Sodium Fast Reactor (SFR), by using air instead of water as a coolant. The RVCS, which is a system to maintain integrity of concrete structures, can be used for reactor exterior surface cooling. The heat removal by RVCS operation affects and affected by the natural circulation inside sodium pool. Thus, understanding the natural circulation inside sodium pool is important for RVCS performance prediction. In this paper, we numerically investigated similarity laws to figure out the applicability of water tests to actual sodium condition using a commercial CFD code, STAR-CCM+. In this study, 4 different scales, 1/20, 1/10, 1/8 and 1/5 were investigated. In every case the volumetric heat flux of core was identical. For numerical simulation, the geometry and configuration of Prototype Gen-IV Sodium Cooled Fast Reactor (PGFSR) developed in KAERI is chosen as reference, and modeled. For comparison, each similarity laws were compared in terms of temperature field. The simulation and comparison results show that by preserving modified Bousinessq number and Peclet number when reducing the test, the temperature field of reactor can be reproduced. However, the test is too small, the flow resistance due to internal structure acts dominantly, disturbing the flow. Therefore, for better result, such flow resistance which can be occurs at small-scaled experiment, should be taken into account.