Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

Validation of RELAP5 MOD3.3 code for Hybrid-SIT against SET and IET experimental data

  • Yoon, Ho Joon (Department of Nuclear Engineering, Khalifa University of Science and Technology(KUST)) ;
  • Al Naqbi, Waleed (Department of Nuclear Engineering, Khalifa University of Science and Technology(KUST)) ;
  • Al-Yahia, Omar S. (Department of Nuclear Engineering, Khalifa University of Science and Technology(KUST)) ;
  • Jo, Daeseong (School of Mechanical Engineering, Kyungpook National University)
  • Received : 2019.09.24
  • Accepted : 2020.02.12
  • Published : 2020.09.25
Download PDF
⟨ Previous Next ⟩

Abstract

We validated the performance of RELAP MOD3.3 code regarding the hybrid SIT with available experimental data. The concept of the hybrid SIT is to connect the pressurizer to SIT to utilize the water inside SIT in the case of SBO or SB-LOCA combined with TLOFW. We investigated how well RELAP5 code predicts the physical phenomena in terms of the equilibrium time, stratification, condensation against Separate Effect Test (SET) data. We also conducted the validation of RELAP5 code against Integrated Effect Test (IET) experimental data produced by the ATLAS facility. We followed conventional approach for code validation of IET data, which are pre-test and post-test calculation. RELAP5 code shows substantial difference with changing number of nodes. The increase of the number of nodes tends to reduce the condensation rate at the interface between liquid and vapor inside the hybrid SIT. The environmental heat loss also contributes to the large discrepancy between the simulation results of RELAP5 and the experimental data.

Keywords

References

  1. I.S. Jeon, S. Heo, H.G. Kang, Optimal operation of hybrid-SITs under a SBO accident, Nucl. Eng. Des. 297 (2016) 136-147. https://doi.org/10.1016/j.nucengdes.2015.11.038
  2. S.I. Lee, H.C. No, Assessment of RELAP5/MOD3.1 for direct-contact condensation in the core makeup tank of the CARR passive reactor, Ann. Nucl. Energy 24 (1997) 445-562.
  3. T. Kwon, C.K. Park, Hybrid SIT for passive safety system, in: Trans. of the KNS Spring Meeting, Gwangju, Korea, 2013. May 30-31.
  4. S.I. Lee, H.C. No, Improvement of direct contact condensation model of RELAP5/MOD3.1 for passive high-pressure injection system, Ann. Nucl. Energy 25 (1998) 677-688. https://doi.org/10.1016/S0306-4549(97)00115-1
  5. S.U. Ryu, H.R. Ryu, H.S. Park, S.J. Yi, An experimental study on the thermalhydraulic phenomena in the Hybrid Safety Injection Tank using a separate effect test facility, Ann. Nucl. Energy 92 (2016) 211-227. https://doi.org/10.1016/j.anucene.2016.02.001
  6. J.B.Lee et al, reportDescription Report of ATLAS Facility and Instrumentation (Second Revision), KAERI/TR-7218/2018.
  7. W. Al Naqbi, H.J. Yoon, Y. Addad, A. Al Kaabi, RELAP5 simulation of core makeup system against OECD-ATLAS experimental data., in: International Congress on Advances in Nuclear Power Plants-2019(ICAPP 2019), Antibes-Juan Les Pins, France, 2019. May 12 - 15 May.
  8. Y.S. Kim, H.S. Park, S. Cho, K.H. Kang, Overall thermal-hydraulic behavior in an SBO test using HSIT in the ATLAS facility, Ann. Nucl. Energy 130 (2019) 250-258. https://doi.org/10.1016/j.anucene.2019.02.050
  9. Nuclear Safety Analysis Division, RELAP5/MOD3.3 Code Manual Vol. I: Code Structure, System Models, and Solution Methods, Idaho National Engineering and Environmental Laboratory, USA, 2001.
  10. S.H. Jang, W.P. Beak, Nucl. Saf. (2010) 296-315. Chungmoonguk.
  11. K.Y. Choi, et al., Comparison Report of Open Calculations for ATLAS Domestic Standard Problem (DSP-01), KAERI/TR-4073, 2010.
  12. K.Y. Choi, et al., Effects of break size on DVI line break accidents of the ATLAS, Nucl. Technol. 175 (2011) 604-618. https://doi.org/10.13182/NT11-A12509
  13. K.Y. Choi, et al., OECD/NEA/CSNI International Standard Problem No. 50: Final Integration Report Volume I, II, III, Analysis of Blind/Open Calculations, NEA/CSNI/R, 2012, p. 6.
  14. K.Y. Choi, et al., A summary of 50th OECD/NEA/CSNI international standard problem exercise (ISP-50), Nucl. Eng. Technol. 44 (6) (2012) 561-586. https://doi.org/10.5516/NET.02.2012.708