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Design of 1/4 Scale Performance Test Facility for the PMR200 RCCS

[+] Author Affiliations
Y. Y. Bae, B. H. Cho, J. H. Kim, M. H. Kim, Y. W. Kim

Korea Atomic Energy Research Institute, Daejeon, Korea

Paper No. ICONE22-30250, pp. V02AT09A027; 8 pages
  • 2014 22nd International Conference on Nuclear Engineering
  • Volume 2A: Thermal Hydraulics
  • Prague, Czech Republic, July 7–11, 2014
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-4590-5
  • Copyright © 2014 by ASME


One of the key technologies for the development of the PMR200, a VHTR demonstration plant, is a verification of the reactor cavity cooling system (RCCS) performance, which ensures reactor safety by passively removing heat from the reactor cavity. A preliminary numerical analysis of the RCCS showed that the maximum temperature in RCCS reached up to 700°C. Since radiation dominates the heat transfer at such a high temperature, it should be considered in both the design and associated numerical works for the test facility. For a verification of the RCCS performance, a 1/4 scale test facility has been constructed, and a performance test is being carried out. As the first step for the design of the test facility, a scaling analysis has been performed; and the ratio of variables between the model and prototype were determined. Numerical calculations using a CFD code were also performed to support the scaling analysis. It was confirmed that the scaling analysis was reasonably correct.

Copyright © 2014 by ASME



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