On some salient unresolved issues in severe accidents for advanced light water reactors

Nuclear Engineering and Design

Volumn 235, Issue 17-19, 2005, Pages 2055-2069

  Song, J H ^a   Kim, S B ^a   Kim, H D ^a  

^a Korea Atomic Energy Research Institute   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

COMBUSTION; COMPUTER SIMULATION; COOLING; HYDROGEN; LIGHT WATER REACTORS; MATHEMATICAL MODELS; NUCLEAR POWER PLANTS; PRESSURE EFFECTS; QUENCHING; RISKS; STEAM; THERMAL EFFECTS;

EXTERNAL REACTOR VESSEL COOLING (ERVC); IN VESSEL RETENTION (IVR); REACTOR VESSELS; THERMAL ATTACKS;

NUCLEAR REACTOR ACCIDENTS;

EID: 23744512554     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2005.05.018     Document Type: Article

References (29)

1. H. Alsmeyer, T. Cron, G. Messemer, and W. Hafner ECOKATS-2, A large scale experiment on melt spreading and subsequent cooling by top flooding Proceedings of ICAPP'04, Paper 4134 Pittsburgh, PA, USA 2004
2. Carbiener, W.A. et al., 1975. Appendix VIII in Reactor Safety Study, WASH-1400, NUREG-75/014.
3. X. Chen, R. Luo, W.W. Yuen, Yuen, and T.G. Theofanous Experimental simulation of microinteractions in large scale explosions Proceedings of the OECD/CSNI specialist meeting on fuel coolant interactions JAERI-Tokai, Japan 1997 364 390
4. Cheung, F.B., Liu, Y.C., 1999. Effects of thermal insulation on external cooling of reactor vessels under severe accident conditions, CD-ROM publication of NURETH-9, California, USA.
5. Cho, D.H., Armstrong, D.R., Gunther, W.H., 1998. Experiments on interactions between zirconium-containing melt and water, NUREG/CR-5372.
6. M.T. Farmer, B.W. Spencer, D.J. Kilsdonk, and R.W. Aeschlimann Results of MACE core coolability experiments M0 and M1b, ICONE-8175 Proceedings of ICONE-8 Baltimore, MD, USA, April 2-6 2000
7. S.W. Hong, Y.S. Shin, J.H. Song, and S.H. Chang Performance test of quenching meshes for hydrogen control J. Nucl. Sci. Technol. 40 10 2003 814 819
8. I. Huhtiniemi, D. Magallon, and H. Hohmann Results of recent KROTOS FCI tests: alumina versus corium melts Nucl. Eng. Design 189 1999 379 389
9. I. Huhtiniemi, and D. Magallon Insight into steam explosions with corium melts in KROTOS Nucl. Eng. Design 204 2001 391 400
10. K.H. Kang, J.H. Kim, S.B. Kim, and H.D. Kim Proceedings of OECD/CSNI Workshop on In-Vessel Core Debris Retention and Coolability Garching, Germany Experimental investigations on in-vessel debris coolability through inherent cooling mechanisms 1998
11. K.H. Kang Proceedings of the third Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety Keyongju An experimental study on in-vessel corium retention through gap cooling using above 200 kg of simulant melt 2002
12. C.S. Kim, and K.Y. Suh Sensitivity studies on thermal margin of reactor vessel lower head during a core melt accident J. Korean Nucl. Soc. 32 4 2000 379 394
13. Kim, H.J. et al., 2002. A study on quenching meshes as a possible controlling tool of hydrogen explosion in nuclear power plants, ICONE10-22232, Arlington.
14. King, D.B., Nicolette, V.F., Dandini, V.J., Spletzer, B.L., 1988. Safety related equipment survival in hydrogen burns in large dry PWR containment buildings, NUREG/CR-4763.
15. K.M. Koo Multi-layered gap measurement on in-vessel corium retention using ultrasonic wave reflective pattern analysis and frequency diversity signal processing J. Korean Soc. Nondestructive Testing 20 4 2000
16. Magallon, D., Huhtiniemi, I., 2001. Energetic event in fuel coolant interaction test FARO L-33, ICONE-9, Nice, France.
17. D. Magallon, and Huhtiniemi Corium melt quenching tests at low pressure and subcooled water in FARO Nucl. Eng. Design 204 2001 369 376
18. J. Miettinen Analysis of two-phase flow phenomena with FLUENT-4 code in the experiments for advanced light water reactor safety Proceedings of the International Congress on Advanced Nuclear Power Plants Hollywood, Florida, USA 2002
19. S.J. Oh Proceedings of the Workshop on In-Vessel Retention for the KNGR Severe Accident Management KEPRI, Taejon, Korea The role of IVR from the severe accident management perspective 1999
20. R.J. Park Experimental study on critical power in a hemispherical narrow gap Nucl. Technol. 140 2002 266 278
21. J.H. Scobel In-vessel retention of molten core debris in the Westinghouse AP1000 advanced passive PWR Proceedings of the International Congress on Advanced Nuclear Power Plants Hollywood, Florida, USA 2002
22. B.R. Segal, A. Giri, U.A. Chikkanagoudar, and A. Karbojian Proceedings of ICAPP'04 Pittsburgh, PA, USA Experiments on in-vessel coolability in the EC-FOREVER program 2004
23. Sehgal, B.R., 1999. Accomplishments and Challenges of the Severe Accident Research, NURETH-9, San Francisco, USA.
24. J.H. Song Spontaneous steam explosions observed in the fuel coolant interaction experiments using reactor material J. Korean Nucl. Soc. 33 4 2002 344 357
25. J.H. Song, S.B. Kim, and H.D. Kim An analysis of the external cooling of the reactor vessel during severe accidents Nucl. Technol. 138 1 2002 79 89
26. 2 mixture Nucl. Eng. Design 222 2003 1 15
27. T.G. Theofanous In vessel coolability and retention of a core melt Nucl. Eng. Des. 169 1997 1 48
28. Travers, W.D., 1998. Options for risk-informed revisions to 10CFR 50 - Domestic licensing of production and utilization facilities. U.S. Nuclear Regulatory Commision, SECY-98-300.
29. N. Yamano, Y. Maruyama, T. Kudo, A. Hidaka, and J. Sugimoto Phenomenological studies on melt-coolant interactions in the ALPHA program Nucl. Eng. Design 155 1995 369 389