Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Similarity evaluation of the pump simulation loop in STELLA-2 for conservation of mechanical sodium pump characteristics

  • Received : 2022.04.28
  • Accepted : 2022.09.21
  • Published : 2023.01.25
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Abstract

The STELLA-2 is a large-scale sodium thermal-hydraulic integral effect test facility and supports the development of PGSFR. The facility adopted Pump Simulation Loop System (PSLS) concept for the mechanical sodium pump in the reference reactor to control and to measure the primary sodium flow. Since the component (mechanical pump) is replaced by the loop, it is very important to evaluate the similarity between the pump and the loop. In this paper, to simulate the characteristic of the mechanical sodium pump, the pressure loss along the various options of the loop was evaluated and the comprehensive validity of each design options was analyzed. Using the similarity criteria based on the Richardson number and Euler number conservation, the PSLS design was finalized and the result was within the acceptable error range. Finally, the result of this study was used for construction of the overall facility, STELLA-2.

Keywords

Acknowledgement

This work was supported by the National Research Foundation of Korea (NRF) (2021M2E2A2081063 and 2021M2D1A1084836) and the National Research Council of Science & Technology (NST) (No. CAP20032-100) grant funded by the Korea government (Ministry of Science and ICT).

References

  1. J. Yoo, et al., Status of Prototype Gen-IV Sodium Cooled Fast Reactor and its Perspectives, Transaction of the KNS Autumn meeting, Gyeongju, Korea, 2015. Oct. 29-30. 
  2. J. Eoh, et al., Computer Codes V&V Tests with a Large-Scale Sodium Thermal-hydraulic Test Facility (STELLA), American Nuclear Society 2016 Annual Meeting, New Orleans, US, 2016. Jun. 12-16. 
  3. J. Hong, et al., Heat transfer performance test of PDHRS heat exchangers of PGSFR using STELLA-1 facility, Nucl. Eng. Des. 313 (2017) 73-83.  https://doi.org/10.1016/j.nucengdes.2016.11.035
  4. J. Lee, et al., Experimental study of sodium heat exchanger performance at high Pe number condition using STELLA-1 facility, Nucl. Eng. Des. 340 (2018) 62-67.  https://doi.org/10.1016/j.nucengdes.2018.09.026
  5. H. Kim, et al., Design and thermal-hydraulic evaluation of the finned-tube type sodium-to-air heat exchanger in sodium test facility, Nucl. Eng. Des. 366 (2020) article 110755. 
  6. J. Lee, et al., Design evaluation of large-scale sodium integral effect test facility (STELLA-2) using MARS-LMR, Ann. Nucl. Energy 120 (2018) 845-856.  https://doi.org/10.1016/j.anucene.2018.07.006
  7. J. Yoon, et al., Heat transfer characteristics of redan structure in large-scale test facility STELLA-2, Nucl. Eng. Technol. 53 (2021) 1109-1118.  https://doi.org/10.1016/j.net.2020.09.006
  8. 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
  9. 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
  10. L.F. Moody, N.J. Princeton, Friction factors for pipe flow, Trans. ASME 66 (8) (1944) 671-684.  https://doi.org/10.1115/1.4018140
  11. C.F. Colebrook, C.M. White, Experiments with fluid friction in roughened pipes, Proc. Roy. Soc. Lond. Math. Phys. Sci. 161 (906) (1937) 367-381.  https://doi.org/10.1098/rspa.1937.0150
  12. C.F. Colebrook, Turbulent flow in pipes, with particular reference to the transition region between the smooth and rough pipe laws, J. Inst. Civ. Eng. 11 (4) (1939) 133-156.  https://doi.org/10.1680/ijoti.1939.13150
  13. Software Version 7.8, FloMASTER User Guide, Mentor Graphics, 2014. 
  14. 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.