The KSFM Journal of Fluid Machinery (한국유체기계학회 논문집)

Korean Society for Fluid machinery (한국유체기계학회)
권호 표지
DOI QR코드

DOI QR Code

Study on Scaling Analysis and Design Methodology of Passive Injection Test Facility

피동 주입 시험 장치의 척도 해석 및 설계 방법론 연구

  • Received : 2016.05.02
  • Accepted : 2016.06.09
  • Published : 2016.10.01
Download PDF
⟨ Previous Next ⟩

Abstract

A design methodology of the modeled test facility to conserve an injection performance of a passive safety injection system is proposed. This safety injection system is composed of a core makeup tank and a safety injection tank. Individual tanks are connected with pressure balance line on the top side and injection line on the bottom side. It is important to conserve the scaled initial injection flow rate and total injection time since this system can be operated by small gravity head without any active pumps. Differential pressure distribution of the injection line induced by the gravity head is determined by the vertical length and elevation of each tank. However, the total injection time is adjustable by the flow resistance coefficient of the injection line. The scaling methodology for the tank and flow resistance coefficient is suggested. A key point of this test facility design is a scaling analysis for the flow resistance coefficient. The scaling analysis proposed on this paper is based on the volume scaling law with the same vertical length to the prototype and can be extended to a model with a reduced vertical length. A set of passive injection test were performed for the tanks with the same volume and the different length. The test results on the initial flow rate and total injection time showed the almost same injection characteristics and they were in good agreement with the design values.

Keywords

References

  1. Tower, S. N., Schulz, T. L., and Vijuk, R. P., 1988, "Passive and Simplified System Features for the Advanced Westinghouse 600 MWe PWR," Nuclear Engineering and Design, Vol. 109, No. 1, pp. 147-154. https://doi.org/10.1016/0029-5493(88)90153-7
  2. Sutharshan, B., Mutyala, M., Vijuk, R. P., and Mishra, A., 2011, "The AP1000 Reactor: Passive Safety and Modular Design," Energy Procedia, Vol. 7, pp. 293-302. https://doi.org/10.1016/j.egypro.2011.06.038
  3. Tuunanen, J., Vihavainen, J., D'Auria, F., and Kimber, G., 1999, "Assessment of Passive Safety Injection Systems of ALWRs," Final Report of the European Commission 4th Framework Programme Project FI4I-CT95-0004, Technical Research Centre of Finland.
  4. Tuunanen, J., Riikonen, V., Kouhia, J., and Vihavainen, J., 1998, "Analyses of PACTEL Passive Safety Injection Experiments GDE-21 Through GDE-25," Nuclear Engineering and Design, Vol. 180, No. 1, pp. 67-91. https://doi.org/10.1016/S0029-5493(97)00306-3
  5. Vihavainen, J. and Tuunanen, J., 2002, "PACTEL Passive Safety Injection Experiments and APROS code Analysis," Natural Circulation Data and Methods for Advanced Water Cooled Nuclear Power Plant Desings, IAEA-TECDOC-1281, Vienna, Austria, pp. 183-194.
  6. Zejun, X., Wenbin, Z., Hua, Z, Bingde, C., Guifan, Z., and Dounan, J., 2003, "Experimental Research Progress on Passive Safety Systems of Chinese Advanced PWR," Nuclear Engineering and Design, Vol. 225, No. 2, pp. 305-313. https://doi.org/10.1016/S0029-5493(03)00178-X
  7. IAEA, 2012, "Summary on Natural Circulation Phenomena Observed in ROSA/AP600 Tests," Natural Circulation Phenomea and Modeling for Advanced Water Cooled Reactors, IAEA-TECDOC-1677, Vienna, Austria, pp. 286-298.
  8. Chang, S. H., No, H. C., and Baek, W. P., 1998, "Development of an Evolutionary Passive PWR Concept: CP-1300," IAEA-SM-353/21P, pp. 111-113.
  9. Lee, S. I. and No, H. C., 1998, "Gravity-driven Injection Experiments and Direct Contact Condensation Regime Map for Passive High-pressure Injection System," Nuclear Engineering and Design, Vol. 183, No. 3, pp. 213-234. https://doi.org/10.1016/S0029-5493(98)00174-5
  10. Lee, S. I. and No, H. C., 1997, "Assessment of RELAP5/MOD3.1 for Direct-contact Condensation in the Core Makeup Tank of the CARR Passive Reactor," Annals of Nuclear Energy, Vol. 24, No. 7, pp. 553-562. https://doi.org/10.1016/S0306-4549(96)00086-2
  11. Lee, S. I. and No, H. C, 1998, "Improvement of Direct Contact Condensation Model of RELAP5/MOD3.1 for Passive High-pressure Injection System," Annals of Nuclear Energy, Vol. 25, No. 9, pp. 677-688. https://doi.org/10.1016/S0306-4549(97)00115-1
  12. Kim, K. K., Lee, W. J., Choi, S., Kim, H. R., and Ha, J. J., 2014, "The First Licensed Advanced Integral Reactor," Journal of Energy and Power Engineering, Vol. 8, No. 1, pp. 94-102.
  13. Bae, Y., 2014, "System Description for Passive Safety Injection System of SMART," SER-410-FS403-SD, KAERI, KOREA.
  14. Reyes Jr, J. N., 2005, "AP600 and AP1000 Passive Safety System Design and Testing in APEX," Natural circulation in water cooled nuclear power plants; Phenomena, Models, and Methodology for System Reliability Assessments, IAEA-TECDOC-1474, Vienna, Austria, pp. 357-381.
  15. Shin, S. J., 2012, "Calculation of Hydraulic Resistance for Injection Line of Pressure Balanced Safety Injection Tank of SMART," SER-410-FS301-004, KAERI, KOREA.
  16. Ryu, S., 2012, "Calculation of Hydraulic Resistance for Injection Line of Core Makeup Tank of SMART," SER-410-FS301-002, KAERI, KOREA.
  17. Shin, S. J., 2012, "Performance Evaluation of Pressure Balanced Safety Injection Tank of SMART," SER-410-FS301-013, KAERI, KOREA.
  18. Nahavandi, A. N., Castellana, F. S., and Moracdkhanian, E. N., 1979, "Scaling Law for Modeling Nuclear Reactor Systems," Nuclear Science and Engineering, Vol. 72, No. 1, pp. 75-83. https://doi.org/10.13182/NSE79-A19310
  19. Ishii, M. and Kataoka, I., 1983, "Similarity Analysis and Scaling Criteria for LWR's Under Single-Phase and Two-Phase Natural Circulation," NUREG/CR-3267, ANL-83-32, U. S. NRC, Washington, D. C.
  20. Yun, B. J., Kwon, T. S., Song, C. H., Euh, D. J., Chu, I. C., Park, J. K., Cho, H. K., and Park, G. C., 2000, "Development of Scaling Law for the Direct ECC Bypass during LBLOCA Reflood Phase with DVI Safety System," Transactions of the Korean Nuclear Society Spring Meeting, KNS, KOREA.
  21. Yun, B. J., Park, C. K., Song, C. H., Kim, J. T., Kwon, T. S., Jun, H. K., and Cho, S., 1999, "Scientific Design of the Test Facility for the KNGR DVI Line Small Break LOCA," KAERI/TR-1258/99, KAERI, KOREA.
  22. Euh, D. J., Yun, Y. J., Chu, I. C., Lee, J. W., Park, J. C., Kim, J. T., Bae, H., Park, C. K., Kwon, T. S., and Yi, S. J., 2010, "Test Facility for SMART Reactor Flow Distribution," KAERI/TR-4239/2010, KAERI, KOREA.