DOI QR코드

DOI QR Code

Analysis of loss of cooling accident in VVER-1000/V446 spent fuel pool using RELAP5 and MELCOR codes

  • Received : 2022.01.08
  • Accepted : 2022.12.25
  • Published : 2023.08.25

Abstract

Following the Fukushima nuclear disaster, the simulation of accidents in the spent fuel pool has become more noticeable. Despite the low amount of decay heat power, the consequences of the accidents in a spent fuel pool (SFP) can be severe due to the high content of long-lived radionuclides and lack of protection by the pressure vessel. In this study, the loss-of-cooling accident (LOFA) for the VVER-1000/V446 spent fuel pool is simulated by employing RELAP5 and MELCOR 1.8.6 as the best estimate and severe accident analysis codes, respectively. For two cases with different total power levels, decay heat of spent fuels is calculated by ORIGEN-II code. For modeling SFP of a VVER-1000, a qualified nodalizations are considered in both codes. During LOFA in SFP, the key sequences such as heating up of the pool water, boiling and reducing the water level, uncovering the spent fuels, increasing the temperature of the spent fuels, starting oxidation process (generating Hydrogen and extra power), the onset of fuel melting, and finally releasing radionuclides are studied for both cases. The obtained results show a reasonable consistency between the RELAP5 and MELCOR codes, especially before starting the oxidation process.

Keywords

References

  1. AEOI (Atomic Energy Organization of Iran), Final Safety Analysis Report ofBNPP-1, Moscow, 2015.
  2. T.E. Collins, G. Hubbard, Technical Study of Spent Fuel Pool Accident Risk at Decommissioning Nuclear Power Plants, Nuclear Regulatory Commission, Washington, DC, 2000. Report No. NUREG-1738, https://www.nrc.gov/docs/ML0104/ML010430066.pdf.
  3. A. Kaliatka, et al., Analysis of the Processes in Spent Fuel Pools in Case of Loss of Heat Removal Due to Water Leakage, Science and Technology of Nuclear Installations, 2013, https://doi.org/10.1155/2013/598975.
  4. j. Fleurot, et al., Synthesis of spent fuel pool accident assessments using severe accident codes, Ann. Nucl. Energy 74 (2014) 5871, https://doi.org/10.1016/j.anucene.2014.07.011.
  5. M. Adorni, et al., Status Report on Spent Fuel Pools under Loss-Of-Cooling and Loss-Of-Coolant Accident Conditions-Final Report, Organisation for Economic Co-Operation and Development, 2015.
  6. G. Mignot, et al., Large scale experiments simulating hydrogen distribution in a spent fuel pool building during a hypothetical fuel uncovery accident scenario, Nucl. Eng. Technol. 48 (2016) 881-892, https://doi.org/10.1016/j.net.2016.06.005.
  7. O. Coindreau, et al., Severe accident code-to-code comparison for two accident scenarios in a spent fuel pool, Ann. Nucl. Energy 120 (2018) 880-887, https://doi.org/10.1016/j.anucene.2018.06.043.
  8. S. Carlos, F. Sanchez-Saez, S. Martorell, Use of TRACE best estimate code to analyze spent fuel storage pools safety, Prog. Nucl. Energy 77 (2014) 224-238, https://doi.org/10.1016/j.pnucene.2014.07.008.
  9. Z. Huang, W. Ma, Performance of a passive cooling system for spent fuel pool using two-phase thermosiphon evaluated by RELAP5/MELCOR coupling analysis, Ann. Nucl. Energy 128 (2019) 330-340, https://doi.org/10.1016/j.anucene.2019.01.024.
  10. Z. Xiong, et al., Experimental study on the sub-atmospheric loop heat pipe passive cooling system for spent fuel pool, Prog. Nucl. Energy 79 (2015) 40-47, https://doi.org/10.1016/j.pnucene.2014.10.015.
  11. M. Kotouc, Analyses of severe accident sequences in the spent fuel pool of the VVER- 1000 type of reactor with MELCOR 1.8. 6, in: 22nd International Conference on Nuclear Engineering, American Society of Mechanical Engineers Digital Collection, 2014.
  12. V. Оgnerubov, А. Кaliatka, V. Vileiniskis, Features of modelling of processes in spent fuel pools using various system codes, Ann. Nucl. Energy 72 (2014) 497-506, https://doi.org/10.1016/j.anucene.2014.06.021.
  13. А. Кaliatka, V. Оgnerubov, V. Vileiniskis, Analysis of the processes in spent fuel pools of Ignalina NPP in case of loss of heat removal, Nucl. Eng. Des. 240 (2010) 1073-1082, https://doi.org/10.1016/j.nucengdes.2009.12.026.
  14. N.E. Kononen, Spent fuel pool accidents in a nordic BWR, in: 21st International Conference on Nuclear Engineering, American Society of Mechanical Engineers Digital Collection, 2013, https://doi.org/10.1115/ICONE21-15641.
  15. Z. Zhang, Y. Du, K. Liang, Advanced modeling techniques of a spent fuel pool with both RELAP5 and MELCOR and associated accident analysis, Ann. Nucl. Energy 110 (2017) 160-170, https://doi.org/10.1016/j.anucene.2017.06.037, 2017.
  16. S.B. Ludwig, A.G. Croff, ORIGEN2, 1eIsotope Generation and Depletion Code Matrix Exponential Method, Oak Ridge National Laboratory, 1999.
  17. C. Fletcher, R. Schultz, RELAP5/MOD3 Code Manual Volume V, Idaho National Engineering Laboratory, Lockheed Idaho Technologies Company, 1995.
  18. M.F. Young, MELCOR Computer Code Manuals NUREG/CR 6119, Sandia National Laboratories, 2000.
  19. AEOI (Atomic Energy Organization of Iran), Report on Safety Analyses of Bushehr NPP at Extreme External Impacts, Iran, 2012.