Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지

3-Dimensional Analysis of the Steam-Hydrogen Behavior from a Small Break Loss of Coolant Accident in the APR1400 Containment

  • Kim Jongtae (Korea Atomic Energy Research Institute) ;
  • Hong Seong-Wan (Korea Atomic Energy Research Institute) ;
  • Kim Sang-Baik (Korea Atomic Energy Research Institute) ;
  • Kim Hee-Dong (Korea Atomic Energy Research Institute) ;
  • Lee Unjang (forschungszentrum Karlsruhe, IKET) ;
  • Royl P. (forschungszentrum Karlsruhe, IKET) ;
  • Travis J. R. (forschungszentrum Karlsruhe, IKET)
  • Published : 2004.02.01
Download PDF
⟨ Previous Next ⟩

Abstract

In order to analyze the hydrogen distribution during a severe accident in the APR1400 containment, GASFLOW II was used. For the APR1400 NPP, a hydrogen mitigation system is considered from the design stage, but a fully time-dependent, three-dimensional analysis has not been performed yet. In this study GASFLOW code II is used for the three-dimensional analysis. The first step to analysis involving hydrogen behavior in a full containment with the GASLOW code is to generate a realistic geometry model, which includes nodalization and modeling of the internal structures such as walls, ceilings and equipment. Geometry modeling of the APR1400 is conducted using GUI program by overlapping the containment cut drawings in a graphical file format on the mesh view. The total number of mesh cells generated is 49,476. And the calculated free volume of the APR1400 containment by GASFLOW is almost the same as the value from the GOTHIC modeling. A hypothetical SB-LOCA scenario beyond design base accident was selected to analyze the hydrogen behavior with the hydrogen mitigation system. The source of hydrogen and steam for the GASFLOW II analysis is obtained from a MAAP calculation. Combustion pressure and temperature load possibilities within the compartments used in the GOTHIC analysis are studied based on the Sigma-Lambda criteria. Finally the effectiveness of HMS installed in the APR1400 containment is evaluated from the point of severe accident management

Keywords

References

  1. J. R. Travis, et. al., GASFLOW: A Computational Fluid Dynamic Code for Gases, Aerosols, and Combustion, LA-13357-M, FZKA-5994 (1998)
  2. John Travis, et al., 'Theoretical and Computational Models of the GASFLOW-II Code,' Procs. SMiRT-15, Seoul, Korea, August 15-20, Vol. XI, p. XI-157 P. (1999)
  3. KEPCO, Standard Safety Analysis Report (Rev. 1) volume 14 (2001)
  4. Summers, R.M. et al., 'MELCOR Computer Code Manuals,' SNL, NUREG/CR-6119, SAND97-2185 (1997)
  5. Henry, R.E. et al., 'MAAP4-Modular Accident Analysis Program for LWR Plants Code Manual,' FAI (1990)
  6. George, T.L. et al., 'GOTHIC Containment Analysis Package Technical Manual,' Report NAI 8907-06, NAI (1997)
  7. X. Cheng and U. Muller, 'Turbulent Natural Convection Coupled with Thermal Radiation in Large Vertical Channels with Asymmetric Heating,' Int. Journal of Heat and Mass Transfer, Vol. 41, Nol.12, pp.1681-1692, (1998) https://doi.org/10.1016/S0017-9310(97)00303-7
  8. J. Trais and P. Royl, Lecture Notes for GASFLOW Workshop, Daejeon, Korea, Apr. (2001)
  9. P. Royl, et al., 'Analysis of Mitigation Measures during Steam/Hydrogen distributions in Nuclear Reactor Containments with the 3D Field Code GASDLOW,' AECL-11762, NEA/CSNI/R(96)8
  10. P. Royl, et al., 'Status of Development, Validation, and Application of the 3D CFD Code GASFLOW at FZK,' IAEA-OECD Technical Meeting, PISA, 11-14 Nov. (2002)
  11. P. Royl, J.R. Travis, W. Baumann, G. Necker, 'Analysis of Containment Experiments with GASFLOW,' II, NURETH-10, Seoul, Korea, Oct. (2003)
  12. P. Royl, et al., 'Analysis of Steam and Hydrogen distributions with PAR Mitigation in NPP Containments,' Nuclear Engineering and Design Vol.202, pp.231-248, (2000) https://doi.org/10.1016/S0029-5493(00)00332-0
  13. J. Eyink, et al., 'Thermal and Dynamic Loads on the EPR Containment due to Hydrogen Combustion,' Procs. ICONE9, Nice Acropolis France, April 8-12, (2001)
  14. Unjang Lee, et al., 'Three Dimensional Analysis of the Steam-Hydrogen Distribution from a Hypothetical Small Break Severe Loss of Coolant Accident in a VVER 1000 Type reactor Containment Using Gasflow II ,' NURETH-10, Seoul, Korea, Oct. (2003)
  15. J. Kim, et al., 'Modeling of APR1400 containment to Study Hydrogen Behavior Using GASFLOW Code,' Proceedings of KNS Spring Meeting, Kyungjoo, Korea, May (2003)
  16. B.C. Lee, J.W. Park, and S.M. Lee, 'An Evaluation of the Effectiveness of the APR1400 hydrogen Mitigation System Using Sophisticated Lumped Parameter Code with 3-Dimensional Model,' Procs. ICAPP, Spain (2003)