Experiments on in-vessel melt coolability in the EC-FOREVER Program

Nuclear Engineering and Design

Volumn 236, Issue 19-21, 2006, Pages 2199-2210

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

^a ALBANOVA UNIVERSITY CENTER   (Sweden)

Author keywords

[No Author keywords available]

Indexed keywords

COOLING; CREEP; FAILURE (MECHANICAL); HEAT TRANSFER; HEATING; PRESSURE VESSELS; VOLUMETRIC ANALYSIS;

COOLABILITY; CORIUM MELT MIXTURE; NATURAL CIRCULATION; VOLUMETRIC HEATING;

RADIOACTIVE MATERIALS;

EID: 33746626365     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2006.03.056     Document Type: Article

References (30)

1. Asmolov V., et al. 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) (1999) 18
2. Bechta T.V. Water boiling on the corium melt surface under VVER severe accident conditions. Nucl. Eng. Des. 195 (2000) 45-56
3. Chu, T.Y., Pilch, M.M, Bentz, J.H., Ludwigsen, J.S, Lu, W.-Y., 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. Multi-phase flow aspects of fuel-coolant interaction in reactor safety research. Nucl. Eng. Des. 145 (1993) 207-215
6. Epstein, M., 1989. Stability of a Core-Melt Crust. MACE Project, Restricted Report. Fauske and Associates, Inc., April 6.
7. Farmer, M.T., 2005. Presentation at the Progress Meeting of the OECD Project. MCCI, Madrid,, April 6-8.
8. Farmer M.T., Spencer B.W., Binder J.L., and Hill D.J. Status and future direction of the melt attack and coolability experiments (MACE) program at Argonne National Laboratory. 9th International Conference on Nuclear Engineering. ICONE-9697, April 8-12 (2001)
9. Giri A., Karbojian A., and Sehgal B.R. Lower head vessel failure under coupled melt pool convection and creep in American steel. 11th International Conference of Nuclear Engineering. Tokyo, Japan, April 20-23 (2003)
10. Henry R.E., and Dube D.A. 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, June 13-15 (1994) 93-104
11. Henry R.E. A scaling and experimental approach for investigating in-vessel cooling. Proceedings of Twenty-Fourth Water Reactor Safety Information Meeting. Bethesda, MD, October 21-23 (1996) 141-159
12. Henry, R.E., 1996, 1997, 2001. In-Vessel Cooling Experiments; Proof of Principle, Phase II, Phase III respectively. Propriety Reports.
13. Jeong J.H., Park R.J., and Kim S.B. Thermal hydraulic phenomena relevant to global dry-out in a hemispherical narrow gap. Heat Mass Transfer 34 (1998) 321-328
14. Köhler W., Schmidt H., Herbst O., and Krätzer W. Experiments on heat removal in a GAP between debris crust and RPV wall. OECD/CSNI Workshop in In-Vessel Core Debris Retention and Coolability NEA/CSNI/R(98)/7th International Conference on Nuclear Engineering, ICONE 7012. Garching, Germany/Tokyo, Japan (1998/2000)
15. Konovalikhin M.J., Yang Z.L., Amjad M., and Sehgal B.R. On Dryout Heat Flux of a Particle Debris Bed with a Downcomer, ICONE-8. Baltimore, USA, April 2-6 (2000)
16. Konovalikhin M.J., and Sehgal B.R. Investigation of Volumetrically Heated Debris Bed Quenching, ICONE 9. Nice, France, April 8-12 (2001)
17. Kymäläinen O., et al. In-vessel retention of corium at the Loviisa plant. Nucl. Eng. Des. 169 (1997) 109-130
18. Lomperski S., and Farmer M.T. Corium Quench Rate Measurements with the SSWICS Facility, NURETH-10. Seoul, Korea, October 5-9 (2003)
19. Maruyama Y., et al. Experimental study on in-vessel debris coolability in ALPHA program. Nucl. Eng. Des. 187 (1999) 241-254
20. Magallon D., and Hohmann H. High pressure corium melt quenching tests in FARO. Nucl. Eng. Des. 155 (1995) 207-215
21. Magallon D., and Hohmann H. Experimental investigation of 150 kg scale corium melt jet quenching in water. Nucl. Eng. Des. 177 (1997) 321-337
22. Sehgal B.R., Nourgaliev R.R., Dinh T.N., and Karbojian A. FOREVER experimental program on reactor pressure vessel creep behaviour and core debris retention. Proceedings of 15th International Conference on Structural Mechanics in Reactor Technology (SMiRT-15). Seoul, Korea, August 16-20 (1999)
23. Sehgal B.R., Nourgaliev R.R., and Dinh T.N. Characterization of heat transfer processes in a melt pool convection and vessel-creep experiment. Nucl. Eng. Des. 211 (2002) 173-187
24. Sehgal B.R., et al. Assessment of reactor vessel integrity. Nucl. Eng. Des. 2753 (2003) 1-31
25. Sehgal B.R., et al. Assessment of reactor vessel integrity (ARVI). Nucl. Eng. Des. 235 (2005) 213-232
26. Suh K.Y., et al. The SONATA-IV project in pursuit of in-vessel defence-in-depth against a severe accident. Proceedings of 11th KAIF/KNS Annual Conference. Seoul, Korea, April 11-12 (1996) 841-853
27. Theerthan S.A., Karbojian A., and Sehgal B.R. FOREVER experiments on thermal and mechanical behaviour of reactor pressure vessel during a severe accident. The EC-FOREVER-1 test. Proceedings of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16). Washington, DC, USA, August 12-17 (2001)
28. Theerthan, S., Giri, A, Karbojian, A., Sehgal, B.R., 2002. EC-FOREVER Experiments on Thermal and Mechanical Behaviour of a Reactor Pressure Vessel during a Severe Accident. Technical Report: EC-FOREVER-3 Test, SAM-ARVI-D016, EC 5th EURATOM Framework Program, February.
29. Thinnes G.L., Korth G.E., Chavez S.A., and Walker T.J. High temperature creep and tensile data for pressure vessel steels SA533B1 and SA508-CL2. Nucl. Eng. Des. 148 (1994) 343-350
30. Willschuetz, H.-G., 2003. Institute of Safety Research, Forschungszentrum Rossendorf, Dresden, Germany, Unpublished Report.