Transactions of the Korean Society of Mechanical Engineers B (대한기계학회논문집B)

The Korean Society of Mechanical Engineers (대한기계학회)
권호 표지
DOI QR코드

DOI QR Code

Simulated Experiments on High Pressure Melt Ejection in the Reactor Cavity During Severe Accident

원자로 가상사고시(노심) 용융물 고압 분출 모의 실험 연구

  • Published : 2000.11.01
Download PDF
⟨ Previous Next ⟩

Abstract

Simulated experiments of high pressure melt ejection(HPME) are performed to measure the released fraction of corium simulant from the French type PWR cavity. The experiments are carried out on a 1/20th linear scaled model of the Ulchin 1&2 cavity. Water or woods metal and nitrogen is used as simulant of molten corium and steam, respectively. Experimental parameters are water mass, annulus area and breach size. It is shown that only breach size effects is very important while the mass and the annulus area do not affect the released fraction. It is found that the liquid film transport is much more dominant mechanism than the entrainment droplet transport, especially in linear scale down simulated HPME experiment.

Keywords

References

  1. Pilch, M. M., Yan, H. and Theofanous, T.G., 1994, 'The Probability of Containment Failure by Direct Containment Heating in Zion,' NUREG/CR-6075, SAND93-1535, Sandia National Laboratories
  2. Plich, M. M. et al., 1995, 'The Probability of Containment Failure by Direct Containment Heating in Surry,' NUREG/CR-6109, SAND93-2078, Sandia National Laboratories
  3. Blanchat, T.K. and Allen, M.D., 1996, 'Experiments to Investigate DCH Phenomena with Large-Scale Models of the Zion and Surry Nuclear Power Plants,' Nuclear Engng. and Design, Vol. 164, pp. 147-174 https://doi.org/10.1016/0029-5493(96)01218-6
  4. Binder, J.L. and Spencer, B.W., 'Investigations into the physical Phenomena and Mechanisms that Effect Direct Containment Heating Loads,' Nuclear Engng. and Design, Vol. 164, pp. 175-199 https://doi.org/10.1016/0029-5493(96)01219-8
  5. Lopez de Bertodano, M. et al., 1996, 'DCH Dispersal and Entrainment Experiment in a Scaled Annular Cavity,' Nuclear Engng. and Design, Vol. 164, pp. 271-285 https://doi.org/10.1016/0029-5493(96)01223-X
  6. Wu, Q., Zhang, G.J., Ishii, M., Revankar, S.T. and Lee, R.Y., 1996, 'Experimental Simulation of Corium Dispersion Phenomena in Direct Containment Heating,' Nuclear Engng. and Design, Vol. 164, pp. 237-255 https://doi.org/10.1016/0029-5493(96)01221-6
  7. Wu, Q., Kim, S., Ishii, M., Revankar, S.T. and Lee, R.Y., 1996, 'High Pressure Simulation Experiment on Corium Dispersion in Direct Containment Heating,' Nuclear Engng. and Design, Vol. 164, pp. 257-269 https://doi.org/10.1016/0029-5493(96)01222-8
  8. Kim, M. H., Chung, C. Y., Kim, H. D. and Kim, S. B., 1992, 'Experimental Study on Direct Containment Heating Phenomena,' Proceeding on the Third Workshop on Severe Accident in Japan, Nov. 4-6, Tokyo, Japan, JAERI-memo 05-100
  9. Chun, M. H., So, D. S. and Lee, C. S., 1991, 'A Experimental Parametric Study of the High Pressure Melt Ejection From Two Different Scale Reactor Cavity Models,' Int. Comm. Heat Mass Transfer, Vol. 18, pp. 619-620 https://doi.org/10.1016/0735-1933(91)90075-F
  10. Kim, S.-B. et al., 1995, 'A Parametic Study of Geometric Effect on the Debris Dispersal from a Reactor Cavity during High Pressure Melt Ejection,' International Com. in Heat and Mass Transfer, Vol. 22, No. 1, pp. 25-34 https://doi.org/10.1016/0735-1933(94)00049-Q
  11. 김도형, 이규정, 김상백, 박래준, 1997, '울진 1,2호기 원전에 대한 노심용융물 고압분출실험 연구,'대한기계학회 '97 추계학술대회논문집, pp. 186-190
  12. 정한원, 이규정, 김상백, 박래준, 1998, '노심 용융물 고압 분출 모의 실험에 관한 해석적 연구,' 대한기계학회 1998년도 추계학술대회논문집 B, pp. 900-905