Development of debris coolability analysis module in severe accident analysis code sampson for impact project

Journal of Nuclear Science and Technology

Volumn 36, Issue 10, 1999, Pages 940-951

  Ujita, Hiroshi ^a   Hidaka, Masataka ^b   Susuki, Akira ^b   Ishida, Naoyuki ^b  

^a Nuclear Power Engineering Corp   (Japan)

^b HITACHI LTD   (Japan)

Author keywords

Core melt; In vessel retention; Melting; Molten debris cooling; Natural circulation; Natural convection; Numerical simulation; Reactor safety; Severe accident; Solidification; Spreading

Indexed keywords

ACCIDENT PREVENTION; COMPUTER SIMULATION; COOLING; DEBRIS; MELTING; MOLTEN MATERIALS; NATURAL CONVECTION; PRESSURE VESSELS; PROBLEM SOLVING; SOLIDIFICATION; TEMPERATURE DISTRIBUTION;

NATURAL CIRCULATION; SOFTWARE PACKAGE SAMPSON;

CORE MELTDOWN;

EID: 0033327781     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.1999.9726284     Document Type: Article

References (27)

1. Ujita, H., et al: The ‘IMPACT Super-Simulation’Project for exploring NPP fundamental phenomena. 2nd CSNI Specialist Meeting on Simulators and Plant Analyzers, Espoo. Finland, Sep. 1997.
2. 5 for analysis of NPP severe accidents, NURETH8, Kyoto, Japan, Sep. 1997.
3. Ujita, H., et al.: Development of severe accident analysis code SAMPSON in IMPACT project, To be published in J. Nucl. Sci. Technol., 36[11], (1999).
4. Morii, T., et al.: Basic models and verification study on fuel rod heat up and fission product release analysis modules in SAMPSON for the IMPACT project, I CONE-7, Tokyo, K7-2, (1999).
5. Satoh, N., el al.: Development of molten core relocation analysis module MCRA in the severe accident analysis code SAMPSON, Submitted to J. Nucl. Sci. Technol.
6. Vierow, K., et al.: Development of the VESUVIUS code for steam explosion analysis, Part 1: Molten jet breakup modeling, J. Jpn. Soc. Multiphase Flow, 12[3], 242-248 (1998).
7. Suzuki, H., et al: Fundamental experiment and analysis for melt spreading on concrete, ICONE-2, San Francisco, (1993).
8. Allison, C. M., et al.: Design report on SCDAP/RELAP5 model improvements-debris bed and molten pool behavior, ZiVEI-94/0174, (1994).
9. Summers, R. M., et al: MELCOR 1.8.0: A computer code for nuclear reactor severe accident source term and risk assessment, NUREG/CR-5531, (1991).
10. Stickler, L. A., et al: Calculations to estimate the margin to failure in the TMI-2, NUREG/CR-6196, (1994).
11. Nichols, B. D., et al: SOLA-VOF: A solution algorithm for transient fluid flow with multiple free boundaries, 1,4-8355, (1980).
12. Amsden, A. A., Harlow, F. H.: The SMAC method: A numerical technique for calculating incompressible fluid flow, LA-4370, (1970).
13. Meijerink, J., Vorst, H. A.: An iterative solution method for linear systems of which the coefficient matrix is a symmetric M-matrix, Math. Comp., 31, 148-162 (1977).
14. JSME Data Book: Heat Transfer (4th Ed.), (JSME), Maruzen, 128 (1986), [in Japanese].
15. Holman, J. P.: “Heat Transfer”, Me Graw-Hill, (1981).
16. Monde, M., et al: Critical heat flux during natu ral convective boiling in vertical rectangular channels submerged in saturated liquid, Trans. ASME J. Heat Transfer, 104, 300-303 (1982).
17. Stickler, L. A., et al: Calculations to estimate the margin to failure in the TMI-2 vessel, NUR.EG/CR-6196, TMI V(93)£G01, EGG-2733, (1994).
18. Theofanous, T. G., et al: The probability of liner failure in a Mark-1 containment, NUREG/CR-5423, (1991).
19. Benard, C., etal: Moving boundary problem: Heat conduction in the solid phase-change material during melting driven by natural convection in the liquid, Int. J. Heat Mass Transfer, 29[11], 1669-1681 (1986).
20. Nishikawa, K., Fujita, Y.: Dennetsugaku, 183-191(1982), [in Japanese].
21. Broughton, J. M., et al: A scenario of the three mile island unit 2 accident, Nucl Technol., 87, 34-53 (1989).
22. Akers, D. W., McCardell, R. K.: Core materials inventory and behavior. Nucl. Technol., 87, 214-223 (1989).
23. Maruyama, Y., et al: Studies on in-vessel debris coola-bility using aluminum oxide as debris simulant, Proc. Workshop on Severe Accident Research in Japan, Oct. 28-30, 1996, Tokyo, 248-253 (1997).
24. Henry, R. E., Dube, D. A.: Water in the RPV: A mechanism for cooling debris in the RPV lower head, OECD/NEA/CSNI Specialist Meeting on Selected Containment Severe Accident Management Strategies held at Stockholm, Sweden (1994).
25. Stickler, L. A., et al: Calculation to estimate the margin to failure in the TMI-2 vessel, NUREG/CR-6196, TMI V(93)EG01, EGG-2733, (1994).
26. Rempe, J. L., et al.: Investigation of the coolability of a continuous mass of relocated debris to a water-filled lower plenum, INEL-EGG-RAAM-11A45, (1994).
27. Kymalainen, O., et al: Heat flux distribution from a volumetrically heated pool with high Rayleigh number, Nucl Eng. Des., 149, 401-408 (1994).