Nuclear Engineering and Technology

  • 제39권4호
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  • Pages.299-312
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  • 2007
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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THERMAL-HYDRAULIC TESTS AND ANALYSES FOR THE APR1400'S DEVELOPMENT AND LICENSING

  • 발행 : 2007.08.31
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초록

The program on thermal-hydraulic evaluation by testing and analysis (THETA) for the development and licensing of the new design features in the APR1400 (Advanced Power Reactor-1400) is briefly introduced with a presentation on the research motivation and typical results of the separate effect tests and analyses of the major design features. The first part deals with multi-dimensional phenomena related to the safety analysis of the APR1400. One research area is related to the multidimensional behavior of the safety injection (SI) water in a reactor pressure vessel downcomer that uses a direct vessel injection type of SI system. The other area is associated with the condensation of steam jets and the resultant thermal mixing in a water pool; these phenomena are relevant to the depressurization of a reactor coolant system (RCS). The second part describes our efforts to develop new components for safety enhancements, such as a fluidic device as a passive SI flow controller and a sparger to depressurize the RCS. This work contributes to an understanding of the new thermal-hydraulic phenomena that are relevant to advanced reactor system designs; it also improves the prediction capabilities of analysis tools for multi-dimensional flow behavior, especially in complicated geometries.

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참고문헌

  1. I.S. Kim and D.S. Kim, 'APR1400: Evolutionary Korean Next Generation Reactor', Proc. ICONE-10, Arlington, USA, April 14-18, 2002
  2. C.-H. Song, T.S. Kwon, I.C. Chu, H.G. Jun and C.K. Park, 'Overview of Thermal Hydraulic Test Program for Evaluating or Verifying the Performance of New Design Features in APR1400 Reactor', Proc. ICAPP'-02, Hollywood, Florida, June 9-13, 2002. (See also the website of the THETA program; http://theta.kaeri.re.kr)
  3. C.-H. Song, W.P. Baek, M.K. Chung and J.K. Park, 'Multi -dimensional Thermal-Hydraulic Phenomena in Advanced Nuclear Reactor Systems: Current Status and Perspectives of the R&D Program at KAERI,' Proc. NURETH-10, Seoul, Korea, Oct. 5-9, 2003
  4. MPR Associates, 'Summary of Results from the UPTF Downcomer Injection/Vent Valve Separate Effects Tests: Comparison to Previous Scaled Tests, and Application to Babcock & Wilcox Pressurized Water Reactors', MPR- 1329 (1992)
  5. B.J. Yun, T.S. Kwon, C.-H. Song, D.J. Euh and J.K. Park, 'Air-Water Test on the Direct ECC Bypass during LBLOCA Reflood Phase with DVI: UPTF Test 21-D Counterpart Test', J. KNS, 33, 3 (2001)
  6. T.S. Kwon, C.R. Choi and C.-H. Song, 'Three-dimensional Analysis of Flow Characteristics on the Reactor Vessel Downcomer during the Late Reflood Phase of a Postulated LBLOCA', Nuclear Eng. & Design, 226, pp. 255-265 (2003) https://doi.org/10.1016/S0029-5493(03)00181-X
  7. B.J. Yun, H.K. Cho, D.J. Euh, C.-H. Song and G.C. Park, 'Scaling for the ECC bypass phenomena during the LBLOCA reflood phase', Nuclear Eng. & Design, 231, pp. 315-325 (2004) https://doi.org/10.1016/j.nucengdes.2004.04.005
  8. H.K. Cho, B.J. Yun, C.-H. Song and G.C. Park, 'Twodimensional Modeling of the Direct ECC Bypass in the APR1400 Downcomer', Nuclear Science & Eng., 156, 1 (2007) https://doi.org/10.13182/NSE07-A2681
  9. H.K. Cho, B.J. Yun, C.-H. Song and G.C. Park, 'Experimental Validation of the Modified Linear Scaling Methodology for Scaling ECC Bypass Phenomena in DVI Downcomer', Nuclear Eng. & Design, 235, pp. 2310-2322 (2005) https://doi.org/10.1016/j.nucengdes.2005.04.005
  10. H.K. Cho, B.J. Yun, C.-H. Song and G.C. Park, 'Experimental Study for Multidimensional ECC Behaviors in Downcomer Annuli with a Direct Vessel Injection Mode during the LBLOCA Reflood Phase', J. Nuclear Science & Technology, 42, 6 (2005)
  11. B.J. Yun, T.S. Kwon, D.J. Euh, I.C. Chu, W.M. Park, C.- H. Song and J.K. Park, 'Direct ECC Bypass Phenomena in the MIDAS Test Facility during LBLOCA Reflood Phase', J. KNS, 34, 5 (2002)
  12. T.S. Kwon, B.J. Yun, D.J. Euh, I.C. Chu and C.-H. Song, 'Multi-dimensional Mixing Behavior of Steam-Water Flow in a Downcomer Annulus during LBLOCA Reflood Phase with a DVI Injection Mode', Nuclear Technology, 143, 1 (2003) https://doi.org/10.13182/NT03-A3393
  13. B.D. Chung, 'SBLOCA Analysis using the MARS Code', Private Communication (2003)
  14. B.J. Yun, D.J. Euh and C.-H. Song, 'Investigation of the Downcomer Boiling Phenomena During the Reflood Phase of a Postulated Large-Break LOCA in the APR1400', Nuclear Technology, 156 (2006)
  15. D.W. Lee, H.C. No, E.H. Lee, S.J. Oh and C.-H. Song, 'Experiment and RELAP5 Analysis for the Downcomer Boiling of APR1400 under LBLOCA Reflood Phase', Nuclear Technology, 153, 2 (2006)
  16. D.J. Euh, B.J. Yun and C.-H. Song, 'Benchmarking of Five-Sensor Probe Method for the Measurement of Interfacial Area Concentration', Exp. In Fluids, 41, pp. 463-478 (2006) https://doi.org/10.1007/s00348-006-0174-1
  17. B.J. Yun, D.J. Euh and C.-H. Song, 'Characteristics of downcomer boiling phenomena during the reflood phase of a postulated large break LOCA for the APR1400', Submitted for Publication to Nuclear Eng. & Design (2007)
  18. B.J. Yun, C.-H. Song, K.H. Min., H.K. Cho and G.C. Park, 'Experimental Observations of the Hydraulic Phenomena in the APR1400 Downcomer during the DVI Line Break Accident', Proc. KNS Spring Mtg., Gyeongju, Korea, May 29-30, 2003
  19. T.S. Kwon, C.-H. Song, W.P. Baek and C.R. Choi, 'Boron Mixing Behaviors in a Downcomer Annulus with DVI during a Main Steam Line Break', Proc. ICAPP'05, Seoul, Korea, May 15-19, 2005
  20. C.R. Choi, T.S. Kwon and C.-H. Song, 'Numerical Analysis and Visualization Experiment on Behavior of Borated Water during MSLB with RCP Running Mode in an Advanced Reactor', Nuclear Eng. & Design, 237, pp. 778-790 (2007) https://doi.org/10.1016/j.nucengdes.2006.12.007
  21. Y.S. Kim and C.-H. Song, 'Condensation Regime Map for a 4-Hole Sparger', Proc. ANS Annual Mtg., San Diego CA, June 1-4. 2003
  22. Y.S. Kim, C.H. Song and C.K. Park, 'Overall Review of Steam Jet Condensation in a Water Pool', Energy Eng. J., 12, 2 (2003)
  23. Y.S. Kim, J.W. Park and C.-H. Song, 'Investigation of the Steam-Water Direct Contact Condensation Heat Transfer Coefficients Using Interfacial Transport Models', Int. Comm. Heat & Mass Transfer, 31, 3 (2004)
  24. Y.S. Kim, Y.J. Youn and C.-H. Song, 'Experimental Study of Turbulent Jet Induced by Steam Jet Condensation through a Hole in a Water Tank', Submitted to Energy Eng. J., (2007)
  25. C.K. Park, C.-H. Song and H.G. Jun. 'Experimental Investigation of the Steam Condensation Phenomena due to a Multi-Hole Sparger', J. Nuclear Science & Technology, 44, 4 (2007)
  26. H.S Kang and C.-H. Song, 'CFD Analysis for a Thermal Mixing in a Subcooled Water Pool under a High Steam Mass Flux Discharge Condition', Accepted for Publication to Nuclear Eng. & Design (2007)
  27. H.S. Kang and C.-H. Song, 'CFD Simulation of Steam Discharge Test at a Low Mass Flux Condition in a Subcooled Water', Proc. ANS Annual Mtg., Boston, USA, June 24- 28, 2007
  28. C.K. Park and C.-H. Song, 'Influence of Key Parameters on the APR1400 In-Containment Refueling Water Storage Tank Hydrodynamic Loads', J. Nuclear Science & Technology, 40, 10 (2003)
  29. I.-C. Chu, C.-H. Song, and J.K. Park, 'Performance Evaluation of a Passive Safety Injection Flow Controller for APR1400,' The 13th Pacific Basin Nuclear Conference (PBNC-13), Shenzhen, China, October 21-25, 2002
  30. I.-C. Chu, C.-H Song, B.H. Cho and J.K. Park, 'Development of Passive Flow Controlling Safety Injection Tank for APR1400', Accepted for Publication to Nuclear Eng. & Design (2007)
  31. W.P. Baek, C.-H. Song, B.J. Yun, T.S. Kwon, S.K. Moon, S.J. Lee, 'KAERI Integral Effect Test Program and the ATLAS Design', Nuclear Technology, 152, Nov. (2005)

피인용 문헌

  1. Performance Evaluation of the Safety Analysis Codes for Subcooled Boiling in a Nuclear Reactor Downcomer during the Late Reflood Phase of an LBLOCA vol.164, pp.3, 2008, https://doi.org/10.13182/NT164-368
  2. Paramètres d'écoulement diphasique dans un ébullition a la cuve en acier pendant un refroidissement d'un APRP de APR1400 pp.4, 2009, https://doi.org/10.1051/lhb/2009043
  3. Steam Jet Condensation in a Pool: From Fundamental Understanding to Engineering Scale Analysis vol.134, pp.3, 2012, https://doi.org/10.1115/1.4005144