An Experimental Study on the Mass and Energy Release for a Hot Leg Break LBLOCA During Post Blowdown

  • S.J. Hong (Seoul National University) ;
  • Kim, J.H. (Seoul National University) ;
  • Park, G.C. (Seoul National University)
  • 발행 : 2000.04.01

초록

Hot leg break LBLOCA(Large Break LOCA) had a potential to be a containment maximum pressure accident in YGN3&4, which was induced from excessive conservatism in the CE analysis methodology of mass and energy release. This study conducted mass and energy release experiment for the hot leg break LBLOCA during post blowdown with an integral test facility, SNUF(Seoul National University Facility). This facility simulated YGN 3&4 with volume ratio of 1/1140 based on Ishii's three level scaling. Experiment showed that SI(Safety Injection) water refilled cold leg first and core later. SI water was vaporized in the core, which resulted in the repressurization of reactor. This increase of pressure drove the water in cold leg to flow up half height of U tubes. However, since the water was drained back soon, the release through the SG side broken section by evaporation was negligibly small. This study also provided experimental assessment of RELAP5 results by KAERI for the release through the SG side broken section.

키워드

참고문헌

  1. G.C. Park, et al., 'Review on the Mass and Energy Release Analysis', KINS/HR-093, (1993)
  2. C.W. Kim, et al., 'Development of analysis methodology for hot leg break mass and energy release, KAERI.4, (1995)
  3. Jin Ho Song, Young Min Kwon, Hae Young Jeong, Tech Mo Kim and Sang Jong Lee, 'An Analysis MEthodology for Hot Leg Break Mass and Energy Release', KAERI/TR-746/96, (1996)
  4. KEPCO, 'YGN3&4 FSAR', Chap. 6.
  5. M. Ishii and O. C. Jones Jr., 'Derivation and Application of Scaling Criteria for Two-Phase Flow', Two-Phase Flows and Heat Trasfer Proc. NATO Advanced Study Institute, Istanbul, Turkey, Vol. 1, (1976)
  6. M. Ishii and I. Kadaoka, 'Scaling Laws for Thermal-Hydraulic System under Single Phase and Two Phase Natural Circulation', Nuclear Engineering and Design Vol. 81, pp411-425, (1984) https://doi.org/10.1016/0029-5493(84)90287-5
  7. G. Kocamustafaogullari and M. Ishii, 'Scaling of Two-Phase Flow Transient Using Reduced Pressure System and Simulant Fluid', Nuclear Engineering and Design Vol. 104, pp121-132, (1978) https://doi.org/10.1016/0029-5493(87)90293-7
  8. M. Ishii, et al, 'Scientific Design of Purdue University Multi-Dimensional Integral Test Assembly(PUMA) for GE SBWR', NUREG/CR-6309, (1996)
  9. Y. Y. Hsu, Z. Y. Wang, M. di Marzo and K. Almenas, 'Scaling-Modeling for Small Break LOCA Test Facility', Nuclear Engineering and Design Vol.122, pp.175-194, (1990) https://doi.org/10.1016/0029-5493(90)90205-C
  10. M. Ishii, 'One-Dimensional Drift-Flux Model and Constitutive Equations for Relative motion between Pahses on Various Two Phase Flow Regimes', ANL-77-47. Chap. VIII, (1977)
  11. G. B. Wallis, 'One-Dimensional Two Phase Flow', McGraw-Hill, Chap. 4-5, (1969)
  12. L. S. Tong, 'Boiling Heat Transfer and Two Phase Flow', John Wiley & Sons, Inc. (1965)
  13. Young Min Kwon, Chan Eok Park and Jin Ho Song, 'Comparative mass and Energy Releasea and Containment Analysis for a Large-Break Loss-Of Coolant-Accident using RELAP5/CONTEMPT4 and Design Computer Codes', Nuclear Technology Vol. 122, pp.295-305, (1998)
  14. G.C. Park et al., 'A Verification Esperiment on Hot Leg Break LBLOCA', KAERI, (1996)