Experiments on in-vessel melt coolability in the EC- forever program

Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04

Volumn , Issue , 2004, Pages 917-927

  Sehgal, B R ^a   Giri, A ^a   Chikkanagoudar, U ^a   Karbojian, A ^a  

^a ROYAL INSTITUTE OF TECHNOLOGY   (Sweden)

Author keywords

[No Author keywords available]

Indexed keywords

COOLING; CREEP; EVAPORATION; MELTING; POROSITY; STEAM; STEEL; THERMAL EFFECTS;

COOLABILITY; MELT POOL; STEAM SYSTEMS; TEMPERATURE MELT;

PRESSURE VESSELS;

EID: 14844332772     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (26)

1. ASMOLOV, V. et al., 1999. Experimental Study of heat transfer in the slotted channels at CTF facility, Proceedings of the OECD NEA Workshop on In-vessel core debris Retention and coolability, NEA/CSNI/R(98) 18.
2. BECHTA, T.V., 2000. Water boiling on the corium melt surface under VVER severe accident conditions, Nuclear Engineering and Design, Vol. 195, pp. 45-56.
3. CHU, T.Y., PILCH, M.M, BENTZ, J.H., LUDWIGSEN, J.S, LU, W-Y. AND HUMPHRIES, L.L., 1998. Lower head failure experiments and analyses, NUREG/CR-5582, SAND98-2047.
4. CHU, T.Y. et al., 2002. OLHF 2002, OECD Lower Head Failure Project Final Report, OECD/CSNI/NEA restricted report.
5. CORRADINI, M.L. AND HOHMANN, H., 1993. Multi-phase flow aspects of fuel-coolant interaction in reactor safety research, Nucl. Engg. Des., vol. 145, pp.207-215.
6. EPSTEIN, M., 1989. Stability of a Core-Melt Crust, Fauske and Associates, Inc., MACE project report, Restricted Report, April, 6.
7. FARMER, M.T., et al., 2000, Proceedings Icone-8 Conference on Nuclear Engineering, Baltimore M.D., USA, April 2-6.
8. th Int. Conference Of Nuclear Engineering, Tokyo, Japan, April 20-23.
9. HENRY, R.E. AND DUBE, D.A., 1994. Water in RPV: A mechanism for cooling debris in the RPV lower head, Proceedings of specialist meeting on selected containment severe accident management strategies, Stockholm, Sweden, pp. 93-104, June13-15.
10. HENRY, R.E., 1996. A scaling and experimental approach for investigating in-vessel cooling, Proceedings of Twenty-Fourth water reactor safety information meeting, Bethesda, MD., PP.141-159, October 21-23.
11. JEONG, J.H., PARK, R.J. AND KIM, S.B., 1998. 'Thermal hydraulic phenomena relevant to global dryout in a hemispherical narrow gap, Heat and Mass Transfer, 34, pp. 321-328.
12. th Conference on Nuclear Engineering, Icone 7012, Tokyo, Japan.
13. KONOVALIKHIN, M.J., YANG, Z.L., AMJAD, M. and SEHGAL, B.R., 2000. On Dryout Heat Flux of a Particle Debris Bed with a Downcomer, ICONE-8, Baltimore, USA, April.
14. KYMÄLÄINEN, O, et al., 1997. In-vessel retention of corium at the Loviisa plant, Nucl. Eng. Des., 169, pp.109-130.
15. LAMPRESKI, S. AND FARMER, M.T., 2003. Corium quench rate measurements with the SSWICS facility, NURETH-10, Seoul, Korea, October 5-9.
16. MARUYAMA, Y. et al., 1999. Experimental study on in-vessel debris coolability in ALPHA program, Nucl. Eng. Des., 187, pp.241-254.
17. MEGALLON, D. AND HOHMANN, H., 1997. Experimental investigation of 150 kg scale corium melt jet quenching in water, Nucl. Engg. Des., 177, pp. 321-337.
18. MEGALLON, D. AND HOHMANN, H., 1995. High pressure corium melt quenching tests in FARO, Nucl. Engg. Des., 155, pp.207-215.
19. th International conference on Structural Mechanics in Reactor Technology (SMiRT-15), Seoul, Korea, August.
20. SEHGAL, B. R., NOURGALIEV, R. R. AND DINH, T. N., 2002. Characterization of heat transfer processes in a melt pool convection and vessel-creep experiment, Nucl. Engg. Des. vol. 211, pp. 173-187.
21. SEHGAL, B.R. et al., 2003. Assessment of Reactor Vessel Integrity, Nucl. Engg. Des., 2753, pp.1-31(2003).
22. th KAIF/KNS Annual Conf. Seoul, Korea. April 11-12, pp.841-853.
23. th International conference on Structural Mechanics in Reactor Technology (SMiRT-16), Washington D.C., USA, August.
24. th EURATOM Framework Program, February.
25. THINNES, G.L., KORTH, G.E., CHAVEZ, S.A, and WALKER, T.J., 1994. High temperature creep and tensile data for pressure vessel steels SA533B1 and SA508-CL2, Nucl. Engg. Des., v.148, pp.343-350.
26. WILLSCHUETZ, H.-G. 2003. Institute of safety Research, Forschungszentrum Rossendorf, Dresden,Germany, Unpublished Report.