Rahayu Kusumastuti, Sriyono Sriyono, Mulya Juarsa, Hendro Tjahjono, I. D. Irianto, Topan Setiadipura, D. H. Salimy, A. Hafid



Reaktor Daya Eksperimental (RDE) is an experimental power reactor based on HTGR technology that implements inherent safety system. Its safety systems are in compliance with “defense in depth” philosophy. RDE is also equipped with reactor cavity cooling system (RCCS) used to remove the heat transferred from the reactor vessel to the containment structure. The RCCS is designed to fulfil this role by maintain the reactor vessel under the maximum allowable temperature during normal operation and protecting the containment structure in the event of failure of all passive cooling systems. The performance and reliability of the RCCS, therefore, are considered as critical factors in determining maximum design power level related to heat removal. RCCS for RDE will use a novel shape to efficiently remove the heat released from the RPV through thermal radiation and natural convection. This paper discusses the calculation of RCCS thermal analysis during accident. The RPV temperature must be maintained below 65ºC. The accident is assumed that there is no electricity from diesel generator supplied to the blower. The methodology used is based on the calculation of mathematical model of the RCCS in the passive mode. The heat is released through cavity by natural convection, in which the RCCS is capable to withdraw the heat at the rate of 50.54 kW per hour.

Keywords: Passive safety, RCCS, RDE, Thermal analysis

Full Text:



  1. Sriyono., R. Kusmastuti., S. Bakhri., G. R. Sunaryo. Analysis of helium purification system capability during water ingress accident in RDE. J. Phys.: Conf. Ser. 2018. 962:1.
  2. M. Subekti., S. Bakhri., G. R. Sunaryo. The Simulator Development for RDE Reactor. J. Phys.: Conf. Ser. 2018. 962:1.
  3. S. J. Ball. Overview of Modular HTGR Safety Characterization and Postulated Accident Behavior Licensing Strategy. ORNL.TM. 2014. 187.
  4. Syd. Ball. Sensitivity Studies of Modular High-Temperature Gas-Cooled Reactor (MHTGR) Postulated Accidents. Nucl. Eng. Des. 2006. 236: 454–462.
  5. Kazuhiko Kunitomi, Shusaku Shiozawa. Safety Design. Nucl. Eng. Des. 2004. 233: 45–58.
  6. Bong Goo Kim., Sung Jae Park., Sung Taek Hong. Irradiation Device For Irradiation Testing Of Coated Particle Fuel At Hanaro, Nucl. Eng. Technol. 2013. 45. 7:941-950.
  7. Angelo Frisani. Analysis Of The Reactor Cavity Cooling System For Very High Temperature Gas-Cooled Reactor Using Computational Fluid Dynamics Tools. A Thesis. Texas A&M University . 2010
  8. L. Capone., Y. A. Hassan., R. Vaghetto. Reactor Cavity Cooling System (RCCS) Experimental Characterization. Nucl. Eng. Des. 2011. 241:4775–4782
  9. Angelo Frisani., Yassin A. Hassan. Computation Fluid Dynamics Analysis of The Reactor Cavity Cooling System for Very High Temperature Gas-Cooled Reactors. Ann. Nucl. Energy. 2014. 72:257–267.
  10. F. Gou., F. Chen., Y. Dong. Preliminary phenomena identification and ranking tables on the subject of the High Temperature Gas-cooled Reactor-Pebble Bed Module thermal fluids and accident analysis. Nucl. Eng. Des. 332, 2018: 11–21
  11. R. C. Martineau., R. A. Berry. A preliminary investigation of rapid depressurization phenomena following a sudden DLOFC in a VHTR. Nucl. Eng. Des. 2010. 240:1013–1021.
  12. Hong-Chan wei. Reactor Cavity Cooling System Heat Removal Analysis for a High Temperature Gas Cooled Reactor. Thesis. University of Florida.2009
  13. H. Sato., H. Ohashi, Y.. Tachibana., K. Kunitomi., M. Ogawa. Analysis of core heat removal capability under DLOFC accidents for HTGRs. Nucl. Eng. Des. 2014. 271: 530–536.
  14. Vervey Aldo. Modelling of a passive reactor cavity cooling system (RCCS) for a nuclear reactor core subject to environmental changes and the optimization of the RCCS radiation heat shield. Nucl. Eng. Des. 2011. 245:4821-4828.
  15. Capole L., Hassan Y. Reactor cavity cooling system (RCCS) experimental characterization. Nucl. Eng. Des. 2011. 241: 4775-4782
  16. IAEA-TECDOC-1645. High Temperature Gas Cooled Reactor Fuels and Materials. Vienna. 2010. 18


  • There are currently no refbacks.

PTKRN Digital Library Ristek Mendeley