Open Access
EPJ Web Conf.
Volume 247, 2021
PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
Article Number 02041
Number of page(s) 8
Section Core Analysis Methods
Published online 22 February 2021
  1. U. Rohde et al., “Development and Verification of the Coupled 3D Neutron Kinetics/Thermal-Hydraulics Code DYN3D-HTR for the Simulation of Transients in Block-Type HTGR,” Nuclear Engineering and Design, 251, pp. 412–422 (2012). [Google Scholar]
  2. G. Strydom et al., “Comparison of the PHISICS/RELAP5-3D ring and blockmodel results for phase I of the OECD/NEA MHTGR-350 benchmark,” Nuclear Technology, 193, pp. 15–35 (2016). [Google Scholar]
  3. H.C. Lee, C.K. Jo, and J.M. Noh, “Development of CAPP Code Based on the Finite Element Method for Analysis of VHTR Cores,” Proceedings of HTR2008, Washington, DC, USA, September 28–October 1, 2008 (2008). [Google Scholar]
  4. H.C. Lee, C.K. Jo, and J.M. Noh, “Development of the CAPP Code for the Analysis of Block Type VHTRs,” Transactions of the Korean Nuclear Society Spring Meeting, Taebaek, Korea, May 26–27, 2011 (2011). [Google Scholar]
  5. H.C. Lee, T.Y. Han, C.K. Jo, and J.M. Noh, “Development of the HELIOS/CAPP Code System for the Analysis of Pebble Type VHTR Cores,” Annals of Nuclear Energy, 71, pp. 130–144 (2014). [Google Scholar]
  6. N.I. Tak et al., “A Practical Method for Whole Core Thermal Analysis of Prismatic Gas-Cooled Reactor”, Nuclear Technology, 177, pp. 352–365 (2012). [Google Scholar]
  7. N.I. Tak et al., “Development of a Core Thermo-Fluid Analysis Code for Prismatic Gas Cooled Reactors,” Nuclear Engineering and Technology, 46, pp. 641–654 (2014). [Google Scholar]
  8. H.S. Lim and H.C. No, “GAMMA Multidimensional Multi-Component Mixture Analysis to Predict Air Ingress Phenomena in an HTGR,” Nuclear Science and Engineering, 152, pp. 87–97 (2006). [Google Scholar]
  9. H.S. Lim, General Analyzer for Multi-component and Multi-dimensional Transient Application, GAMMA+ 1.0 Volume II: Theory Manual, KAERI/TR-5728/2014, Korea Atomic Energy Research Institute (2014). [Google Scholar]
  10. N. Tak, H.C. Lee, H.S. Lim, and T.Y. Han, “CAPP/GAMMA+ code system for coupled neutronics and thermo-fluid simulation of a prismatic VHTR core,” Annals of Nuclear Energy, 92, pp. 228–242 (2016). [Google Scholar]
  11. S. Yuk et al., “CAPP/GAMMA+ Coupled Code System for Transient Analysis of a Block-Type HTGR Core,” Proceedings of M&C2019, Portland, Oregon USA, August 25-29, 2019 pp. 1857-1863 (2019). [Google Scholar]
  12. J. Y. Cho et al., DeCART2D v1.1 User’s Manual, KAERI/UM-40/2016, Korea Atomic Energy Research Institute (2016). [Google Scholar]
  13. “CFX version 19.0”, (2018). [Google Scholar]
  14. J. Ortensi et al., Benchmark of the MHTGR-350 MW Core Design. Volumes I and II, NEA/NSC/R(2017)4, Nuclear Energy Agency (2017). [Google Scholar]

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