Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

Heat transfer characteristics of redan structure in large-scale test facility STELLA-2

  • Received : 2020.04.13
  • Accepted : 2020.09.12
  • Published : 2021.04.25
Download PDF
⟨ Previous Next ⟩

Abstract

The construction of STELLA-2 facility is on-going to demonstrate the safety system of PGSFR and to provide comprehensive understanding of transient behavior under DBEs. Considering that most events are single-phase natural circulation flow with slow transient, STELLA-2 was designed with reduced-height of 1/5 length scale. The ratio of volume to surface area in the vessel can relatively increase resulting in excessive heat transfer. Therefore, a steady-state thermal-hydraulic analysis was performed and the effect of design change to reduce the heat transfer through redan was investigated. The heat transfer through single wall redan in STELLA-2 was 3% of the core power, comparable to 1% of the core power in PGSFR. By applying the insulated redan, about 70% of decrease effect was observed. The effect on transient behavior was also evaluated. The conclusion of this study was directly applied to the STELLA-2 design and the modified version is under construction.

Keywords

Acknowledgement

This work was supported by the National Research Foundation (NRF) of Korea grant funded by the Korea government (MSIT - No. 2012M2A8A2025635, MSIT - No. 2016M2B2B1944980, and MOE - No. 2018R1D1A1B07050341).

References

  1. J. Eoh, et al., Computer Codes V&V Tests with a Large-Scale Sodium Thermalhydraulic Test Facility (STELLA), ANS Annual Meeting, New Orleans, USA, 2016. June 12-16.
  2. M. Ishii, et al., The three level scaling approach with application to the Purdue university multi-dimensional integral test assembly (PUMA), Nucl. Eng. Des. 186 (1-2) (1998) 177-211. https://doi.org/10.1016/S0029-5493(98)00222-2
  3. M.P. Heisler, Development of scaling requirements for natural convection liquid-metal fast breeder reactor shutdown heat removal test facilities, Nucl. Sci. Eng. 80 (1982) 347-359. https://doi.org/10.13182/NSE82-A19819
  4. M.P. Heisler, R.M. Singer, Facility Requirements for Natural Convection Shutdown Removal System Testing, Decay Heat Removal and Natural Convection in Fast Breeder Reactor, 1981, pp. 113-127. Menisphere.
  5. Watanabe, O., et al., Development of an evaluation methodology for the natural circulation decay heat removal system in a sodium cooled fast reactor, J. Nucl. Sci. Technol., Vol. 52, pp. 1102-1121. https://doi.org/10.1080/00223131.2014.994049
  6. C.H. Song, et al., Scaling Analysis of the Integral Test Loop to Simulate Korean PWR Plant, Korea Atomic Energy Research Institute, 2001. KAERI/TR-1783/2001.
  7. Task group on advanced reactor experimental facilities (TAREF), Experimental Facilities for Sodium Fast Reactor Safety Studies 12 (2010) 2010. OECD/NEA, NEA/CSNI/R.
  8. J. Lee, et al., Technology Status to Support for the STELLA-2 Program Establishment, Korea Atomic Energy Research Institute, 2014. KAERI/AR-2037/2014.
  9. J. Eoh, et al., Basic Design Report of Sodium Thermal-hydraulic Integral Effect Test Facility (STELLA-2), Korea Atomic Energy Research Institute, 2016. KAERI/TR-6705/2016.
  10. J. Yoon, et al., Evaluation of Thermal-hydraulic Behavior in a Large Sodium Pool of a Scaled-Down Sodium Integral Effect Test Facility, STELLA-2, the 11st International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety, NUTHOS-11), 2014.
  11. J. Lee, et al., Design of electric core simulator system (ECSS) for large-scale integral effect test facility, Ann. Nucl. Energy 133 (2019) 762-776. https://doi.org/10.1016/j.anucene.2019.07.023
  12. K.D. One, Thermal insulation materials, FLEXTHERM - high efficient quilted microporous insulation. http://en.kdone.net/ceratech/product_view?Seq=109.
  13. K. Ha, et al., Development of MARS-LMR and Steady-State Calculation for KALIMER-600, 2007. Technical Report in Korea Atomic Energy Research Institute, KAERI/TR-3418/2007.
  14. Lee, J., et al., Design evaluation of large-scale sodium integral effect test facility (STELLA-2) using MARS-LMR, Ann. Nucl. Energy, Vol. 120, pp. 845-856. https://doi.org/10.1016/j.anucene.2018.07.006