A two-cell equilibrium model for predicting direct containment heating

Nuclear Engineering and Design

Volumn 164, Issue 1-3, 1996, Pages 61-94

  Pilch, Martin M ^a  

^a SANDIA NATIONAL LABORATORIES   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

COOLANTS; DATABASE SYSTEMS; FORECASTING; GEOMETRY; HEAT TRANSFER; MATHEMATICAL MODELS; THERMAL LOAD;

DIRECT CONTAINMENT HEATING; REACTOR COOLANT SYSTEM; TWO CELL EQUILIBRIUM MODEL;

CONTAINMENT VESSELS;

EID: 0030215178     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/0029-5493(96)01230-7     Document Type: Article

References (75)

1. M.D. Allen, R.T. Nichols and M. Pilch, A demonstration experiment of steam-driven, high-pressure melt ejection: the HIPS-10S test, Rep. NUREG/CR-5373, SAND89-1135, 1990 (Sandia National Laboratories, Albuquerque, NM).
2. M.D. Allen, M. Pilch, R.T. Nichols, J.E. Brockmann, D.W. Sweet and W.W. Tarbell, Experimental results of direct containment heating by high-pressure melt ejection into the Surtsey vessel: the DCH-3 and DCH-4 tests, Rep. SAND90-2138 1991a (Sandia National Laboratories, Albuquerque, NM).
3. M.D. Allen, M. Pilch, R.T. Nichols and R.O. Griffith, Experiments to investigate the effect of flight path on direct containment heating (DCH) in the Surtsey test facility: the limited flight path (LFP) tests, Rep. NUREG/CR-5728, SAND91-1105, October 1991b (Sandia National Laboratories, Albuquerque, NM).
4. M.D. Allen, M. Pilch, R.O. Griffith and R.T. Nichols, Experiments to investigate the effect of water in the cavity on direct containment heating (DCH) in the Surtsey test facility - the WC-1 and WC-2 tests, Rep. SAND91-1173, March 1992a (Sandia National Laboratories, Albuquerque, NM).
5. M.D. Allen, M. Pilch, R.O. Griffith and R.T. Nichols, Experimental results of tests to investigate the effects of hole diameter resulting from bottom head failure on direct containment heating (DCH) in the Surtsey test facility - the WC-1 and WC-3 tests, Rep. SAND91-2153, March 1992b (Sandia National Laboratories, Albuquerque, NM).
6. M.D. Allen, M. Pilch, R.O. Griffith, R.T. Nichols and T.K. Blanchat, Experiments to investigate the effects of 1:10 scale Zion structures on direct containment heating (DCH) in the Surtsey test facility: the IET-1 and IET-1R tests, Rep. SAND92-0255, July 1992c (Sandia National Laboratories, Albuquerque, NM).
7. M.D. Allen, M. Pilch, R.O. Griffith, D.C. Williams and R.T. Nichols, The third integral effects test (IET-3) in the Surtsey test facility, Rep. SAND92-0166, June 1992d (Sandia National Laboratories, Albuquerque, NM).
8. M.D. Allen, T.K. Blanchat, M. Pilch and R.T. Nichols, The effects of condensate levels of water on direct containment heating (DCH) in Zion-like geometry: the fourth integral effects test (IET-4) conducted in the Surtsey test facility, Rep. SAND92-1241, September 1992e (Sandia National Laboratories, Albuquerque, NM).
9. M.D. Allen, T.K. Blanchat, M. Pilch and R.T. Nichols, Experimental results of an integral effects test in a Zion-like geometry to investigate the effects of a classically inert atmosphere on direct containment heating: the IET-5 experiment, Rep. SAND92-1623, November 1992f (Sandia National Laboratories, Albuquerque, NM).
10. M.D. Allen, T.K. Blanchat, M. Pilch and R.T. Nichols, An integral effects test in a Zion-like geometry to investigate the effects of pre-existing hydrogen on direct containment heating in the Surtsey test facility - the IET-6 experiment, Rep. SAND92-1802, November 1992g (Sandia National Laboratories, Albuquerque, NM).
11. M.D. Allen, T.K. Blanchat, M. Pilch and R.T. Nichols, An integral effects test to investigate the effects of condensate levels of water and pre-existing hydrogen on direct containment heating in the Surtsey test facility - the IET-7 experiment, Rep. SAND92-2021, November 1992h (Sandia National Laboratories, Albuquerque, NM).
12. M.D. Allen et al., Experiments to investigate the effects of fuel/coolant interactions on direct containment heating: the IET-8A and IET-8B experiments, Rep. SAND92-2849, February 1993 (Sandia National Laboratories, Albuquerque, NM).
13. M.D. Allen et al., Test results on direct containment heating by high-pressure melt ejection into the Surtsey vessel: the TDS test series, Rep. SAND91-1208, 1994a (Sandia National Laboratories, Albuquerque, NM).
14. M.D. Allen et al., Experiments to investigate direct containment heating phenomena with scaled models of the Zion nuclear power plant in the Surtsey test facility, Rep. NUREG/CR-6044, SAND93-1049, 1994b (Sandia National Laboratories, Albuquerque, NM).
15. K.D. Bergeron and D.C. Williams, CONTAIN calculations of containment loading of dry PWRs, Nucl. Eng. Des., 90 (1985) 153.
16. J.L. Binder, L.M. McUmber and B.W. Spencer, Quick look data report on the integral effects test IR in the COREXIT facility at Argonne National Laboratory, draft for review, May 1992a (Argonne National Laboratory, Argonne, IL).
17. J.L. Binder, L.M. McUmber and B.W. Spencer, Quick look data report on the integral effects test IRR in the COREXIT facility at Argonne National Laboratory, draft for review, May 1992b (Argonne National Laboratory, Argonne, IL).
18. J.L. Binder, L.M. McUmber and B.W. Spencer, Quick look data report on the integral effects test-3 in the COREXIT facility at Argonne National Laboratory, draft for review, July 1992c (Argonne National Laboratory, Argonne, IL).
19. J.L. Binder, L.M. McUmber and B.W. Spencer, Quick look data report on the integral effects test-6 in the COREXIT facility at Argonne National Laboratory, draft for review, August 1992d (Argonne National Laboratory, Argonne, IL).
20. J.L. Binder, L.M. McUmber and B.W. Spencer, Quick look data report on the integral effects test-7 in the COREXIT facility at Argonne National Laboratory, draft for review, September 1992e (Argonne National Laboratory, Argonne, IL).
21. J.L. Binder, L.M. McUmber and B.W. Spencer, Quick look data report on the integral effects test-8 in the COREXIT facility at Argonne National Laboratory, draft for review, October 1992f (Argonne National Laboratory, Argonne, IL).
22. J.L. Binder, L.M. McUmber and B.W. Spencer, Direct containment heating experiments in Zion nuclear power plant geometry using prototypic core materials: the UIA and UIB tests, Rep. ANL/RE/LWR 93-3, April 1993a (Argonne National Laboratory, Argonne, IL).
23. J.L. Binder, L.M. McUmber and B.W. Spencer, Direct containment heating experiments in Zion nuclear power plant geometry using prototypic core materials: the UZ test, Rep. ANL/RE/LWR 93-3, May 1993b (Argonne National Laboratory, Argonne, IL).
24. T.K. Blanchat et al., Experiments to investigate direct containment heating phenomena with scaled models of the Surry nuclear power plant, Rep. NUREG/CR-6152, SAND93-2519, April 1994 (Sandia National Laboratories, Albuquerque, NM).
25. M.H. Chun, D.S. So and C.S. Lee, A parametric study of the high pressure melt ejection from two different scale reactor cavity models, Int. Comm. Heat Mass Trans., Vol. 18, 1991, pp. 619-628.
26. CLWG, Estimates of early containment loads from core melt accidents, Rep. NUREG-1079, 1985 (US Nuclear Regulatory Commission, Washington, DC).
27. M.L. Corradini, I. Huhtiniemi, M.H. Kim, G.A. Moses and L.C. Pong, Application of a direct heating model to Sandia Surtsey tests, Rep. UWRSR-50, September 1986 (University of Wisconsin, Madison, WI).
28. S. Darwish, Containment response to direct containment heating in pressurized water reactors, Ph.D. Dissertation, University of Michigan, 1991.
29. G. Fruttuoso, A. Manfredini, F. Oriold, G. Sandrelli and M. Valisi, A model for the analysis of containment behavior during high-pressure melt ejection scenarios, ANS/ENS Int. Conf., Chicago, IL, November 15-20, 1992.
30. T. Ginsberg and N.K. Tutu, Safety research programs sponsored by Office of Nuclear Regulatory Commission, Quarterly Progr. Rep. NUREG/CR-2331, Vol. 7, No. 2, 1987.
31. R.E. Henry, Evaluation of fission product release rates during debris dispersal, PSA 1989, Proc. ANS/ENS Int. Topical Meet.: Probability Reliability and Safety Assessment, 1989, pp. 375-383.
32. R.E. Henry and M.G. Plys, MAAP-3.0B-modular accident analysis program for LWR power plants: user guidance, Rep. EPRI NP-7071-CCML, Vois. 1, 2, and 3, 1990 (Electric Power Research Institute).
33. R.E. Henry et al., Direct containment heating experiments in a Zion-like geometry, in 26th National Heating Transfer Conf. Vol. 87, 1991.
34. IDCOR, Technical support for issue resolution, IDCOR Technical Rep. 85.2, 1985.
35. M. Ishii, S.T. Revankar, G. Zhang, Q. Wu and P. O'Brien, Separate effects experiments on phenomena of direct containment heating - air-water simulation experiments in Zion geometry, Rep. PU NE-93/1, March 1993 (Purdue University, West Lafayette, IN).
36. M. Kim, C. Chung, H. Kim and S. Kim, Experimental study on direct containment heating phenomena, ANS Winter Meet., Chicago, IL, 1992.
37. S. Levy, Debris dispersal from reactor cavity during low temperature simulant tests of direct containment heating. Part I: tests with constant gas flow rates; part II: tests with blowdown gas conditions, Proc. National Heat Transfer Conf., Minneapolis, MN, 1991.
38. R.V. Macbeth and R. Trenberth, Experimental modeling of core debris dispersion from the vault under a PWR pressure vessel - part 1. Preliminary experimental results, Rep. AEEW-R1888, 1987 (Winfrith, UK).
39. R.V. Macbeth et al., Experimental modeling of core debris dispersion from the vault under a PWR pressure vessel -part 3. Results of varying the size scaling factor of the model used, Rep. AEEW-R2426, 1988 (Winfrith, UK).
40. K.D. Marx, A computer model for the transport and chemical reaction of debris in direct containment heating experiments, Nucl. Sci. Eng., 102 (1989) 391.
41. B.W. Morris, CORDE - a model for core debris ejection and dispersal from a PWR pressure vessel (pre-release version 1), Rep. PWR/SAWG/PC(88) 424, 1988 (Winfrith, UK).
42. K.K. Murata, D.E. Carroll, K.E. Washington, F. Gelbard, G.D. Valdez, D.C. Williams and K.D. Bergeron, User's manual for CONTAIN 1.1: a computer code for severe nuclear reactor accident containment analysis, Rep. NUREG/ CR-5026, SAND87-2309, 1990 (Sandia National Laboratories, Albuquerque, NM).
43. M. Pilch, C.A. Erdman and A.B. Reynolds, Acceleration induced breakup of liquid drops, Rep. NUREG/CR-2247, 1981 (US Nuclear Regulatory Commission, Washington, DC).
44. M. Pilch and W.W. Tarbell, Preliminary calculations on direct heating of a containment atmosphere by airborne core debris, Rep. NUREG/CR-4455, SAND85-2439, 1986 (Sandia National Laboratories, Albuquerque, NM).
45. M. Pilch, W.W. Tarbell and J.E. Brockmann, The influence of selected containment structures on debris dispersal and transport following high pressure melt ejection from the reactor vessel, Rep. NUREG/CR-4914, SAND87-0940, September 1988 (Sandia National Laboratories, Albuquerque, NM).
46. M. Pilch, Adiabatic equilibrium models for direct containment heating, Water Reactor Safety Information Meet., Bethesda, MD, 1991 (submitted to Nucl. Eng. Des.).
47. M. Pilch and R.O. Griffith, Gas blowthrough and flow quality correlations for use in the analysis of high pressure melt ejection (HPME) events, Rep. SAND91-2322, June 1992a (Sandia National Laboratories, Albuquerque, NM).
48. M.M. Pilch, M.D. Allen and R.O. Griffith, Kinetic limitations to adiabatic equilibrium models for direct containment heating (DCH), Rep. SAND92-0009C, 28th ASME/AICHE/ ANS National Heat Transfer Conf., San Diego, CA, August 1992b.
49. M.M. Pilch, H. Yan and T.G. Theofanous, The probability of containment failure by direct containment heating in Zion, Rep. NUREG/CR-6075, SAND93-1535, December 1994 (Sandia National Laboratories, Albuquerque, NM).
50. J.L. Rempe, S.A. Chavez, G.L. Thinnes, C.M. Allison, G.E. Korth, R.J. Witt, J.J. Slenicki, S. Kong Wang, C.H. Heath and S.D. Snow, Light water reactor lower head failure analysis, Rep. NUREG/CR-5642, EGG-2618, March 1992 (Idaho National Engineering Laboratory, ID).
51. P.W. Rose, Experimental modeling of core debris dispersion from the vault under a PWR pressure vessel - part 2. Results of including the instrument tubes support structure in the experiment, Rep. AEEW-R2143, 1987 (Winfrith, UK).
52. J.E. Shepard, Analysis of diffusion flame tests, Rep. NUREG/ CR-4534, SAND86-0419, August 1987 (Sandia National Laboratories, Albuquerque, NM).
53. J.J. Sienicki and B.W. Spencer, A multifluid, multiphase flow and heat transfer model for the prediction of sweepout from a reactor cavity, Proc. 4th Miami Int. Symp. on Multi-phase Transport and Particulate Phenomena, Miami Beach, FL, December 15-17, 1986.
54. J.J. Sienicki and B.W. Spencer, The PARSEC computer code for analysis of direct containment heating by dispersed debris, Heat Transfer - Pittsburg 1987, R.W. Lyczkowski (ed.), AIChE Symp. Ser. No. 257, Vol. 83, American Institute of Chemical Engineers, New York, 1987, p. 355.
55. B.W. Spencer et al., Sweepout thresholds in reactor cavity interactions, Rep. ANL/LWR/SAF 82-1, 1982 (Argonne National Laboratory, Argonne, IL).
56. B.W. Spencer et al., Phenomenological investigations of cavity interactions following postulated vessel melt-through, Rep. NUREG/CP-0027, Vol. 2, Proc. Int. Meet. Thermal Nuclear Reactor Safety, Chicago, IL, August 28-September 2, 1983.
57. B.W. Spencer, J.J. Sienicki and L.M. McUmber, Hydrodynamics and heat transfer aspects of corium-water interactions, Rep. EPRI NP-5127, March 1987 (Argonne National Laboratory, IL).
58. D.W. Stamps and M. Berman, High-temperature hydrogen combustion in reactor safety applications, Nucl. Sci. Eng., 109, (1991) 39.
59. R.M. Summers, Letter report summarizing the implementation of the DCH model into MELCOR, Lett. Rep. to NRC, April 15, 1992.
60. D.W. Sweet, K.E. Washington and M. Pilch, Further development of the KIVA-DCH code for the analysis of the transport and chemical reaction of molten debris in direct containment heating experiments, Rep. SAND90-2535, 1991 (Sandia National Laboratories, NM).
61. W.W. Tarbell et al., High-pressure melt streaming (HIPS) program plan, Rep. NUREG/CR-3025, SAND82-2477, 1984 (Sandia National Laboratories, Albuquerque, NM).
62. W.W. Tarbell et al., Pressurized melt ejection into scaled reactor cavities, Rep. NUREG/CR-4512, SAND86-0153, 1986 (Sandia National Laboratories, Albuquerque, NM).
63. W.W. Tarbell et al., Results from the DCH-1 experiment, Rep. NUREG/CR-4871, SAND86-2483, 1987 (Sandia National Laboratories, Albuquerque, NM).
64. W.W. Tarbell et al., DCH-2: results from the second experiment performed in the Surtsey direct heating test facility, Rep. NUREG/CR-4917, SAND87-0976, 1988 (Sandia National Laboratories, Albuquerque, NM).
65. W.W. Tarbell et al., Pressurized melt ejection into water pools, Rep. NUREG/CR-3916, SAND84-1531, March 1991 (Sandia National Laboratories, Albuquerque, NM).
66. T.G. Theofanous and H. Yan, The probability of mark-I liner attack, Presentation at the 20th Water Reactor Safety Information Meet., Bethesda, MD, October 21-23, 1992.
67. N.K. Tutu et al., Debris dispersal from reactor cavities during high pressure melt ejection accident scenarios, Rep. NUREG/CR-5146, BNL-NUREG-52147, 1988a (Brookhaven National Laboratory, Upton, NY).
68. N.K. Tutu et al., Low pressure cutoff for melt dispersal from reactor cavities, Fourth Proc. Nuclear Thermal Hydraulics, 1988b, pp. 29-37.
69. N.K. Tutu, Melt dispersal characteristics of the Watts Bar cavity, Technical Rep. A-3024, April 1990a (Brookhaven National Laboratory, Upton, NY).
70. N.K. Tutu and T. Ginsberg, Letter report on the results of melt dispersal experiments with Surry and Zion cavity models, October 1990b (Brookhaven National Laboratory, Upton, NY).
71. D.C. Williams, K.D. Bergeron, D.E. Carroll, R.D. Gasser, J.L. Tills and K.E. Washington, Containment loads due to direct containment heating and associated hydrogen behavior: analysis and calculations with the CONTAIN code, Rep. NUREG/CR-4896, SAND87-0633, May 1987 (Sandia National Laboratories, Albuquerque, NM).
72. D.C. Williams and D.L. Louie, CONTAIN analyses of direct containment heating events in the Surry plant, Proc. Thermal Hydraulics Division, ANL/ENS Winter Meet., Washington, DC, October 31-November 4, 1988.
73. D.C. Williams, An interpretation of the results of some recent direct containment heating (DCH) experiments in the Surtsey facility, Rep. SAND92-0442C, presented at the NURETH-5 Conf., Salt Lake City, UT, September, 1992.
74. ZPSS, Zion probabilistic safety study, Commonwealth Edison Co., Chicago, IL, 1981.
75. N. Zuber et al., An integrated structure and scaling methodology for severe accident technical issue resolution, draft for comment, Rep. NUREG/CR-5809, EGG-2659, 1992.