Formation, characterisation and cooling of debris. Scenario discussion with emphasis on TMI-2

Nuclear Engineering and Design

Volumn 236, Issue 19-21, 2006, Pages 1955-1964

  Reinke, Nils ^a   Drath, Tilman ^a   Berlepsch, Thilo v ^a   Unger, Hermann E ^a   Koch, Marco K ^a  

^a RUHR UNIVERSITY BOCHUM   (Germany)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; CONTAINMENT VESSELS; INDUSTRIAL MANAGEMENT; LIGHT WATER REACTORS; NUCLEAR REACTOR ACCIDENTS; PROBABILITY;

ACCIDENT MANAGEMENT STRATEGY; MELT PROGRESSION PHENOMENOLOGY; REACTOR VESSELS;

NUCLEAR POWER PLANTS;

EID: 33746626758     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2006.03.029     Document Type: Article

References (20)

1. Akers D.W., and McCardell R.K. Core materials inventory and behaviour. Nucl. Technol. 87 (1989) 214-223
2. Anderson J.L., and Sienicki J.J. Thermal behaviour of molten corium during the TMI-2 core relocation event. Nucl. Technol. 87 (1989) 283-293
3. Bandini G. Status of Degraded Core Issues, NEA/CSNI/R(2001)5 (2000), Nuclear Energy Agency, Paris
4. Broughton J.M., Kuan P., Petti D.A., and Tolman E.L. A scenario of the TMI-2 accident. Nucl. Technol. 87 (1989) 34-53
5. Drath, T., Dapper, M., Kleinhietpaß, I.-D., Unger, H., Koch, M.K., 2004. Calculation of the TMI-2 Accident Using the Code ATHLET-CD (Part 1). Part 1 of the Seventh Technical Report of the Research Project BMWi 150 1241: External Validation of the Code ATHLET-CD by Means of Selected Experiments, LEE-24. Ruhr-University Bochum (RUB), Energy Systems and Energy Economics (LEE), in German.
6. Eidam G.R. The TMI-2 scenario. Proceedings of the Seminar on Fission Transport Processes in Reactor Accidents. Dubrovnik, Yugoslavia (1990) 819-832
7. Epstein M., and Fauske H.K. The TMI-2 core relocation-heat transfer and mechanism. Nucl. Technol. 87 (1989) 1021-1035
8. Henry R.E., and Dube D.A. Water in the RPV: a mechanism for cooling debris in the lower head. In: Frid W. (Ed). Proceedings of the Specialist Meeting on Selected Containment Severe Accident Strategies, SKI Report 95:43 (NEA/CSNI/R(95)3). Stockholm (1995) 93-104
9. Kang K.H., Kim J.H., Kim S.B., Hong J.H., and Kim H.D. Experimental investigations on in-vessel debris coolability through inherent cooling. In-Vessel Core Debris Retention and Coolability (NEA/CSNI/R(98)18) (1998), Nuclear Energy Agency pp. 251-260
10. Linnemann, Th., Koch, M.K., Unger, H., 1998. Review of the TMI-2 Accident and Late Phase SFD Code Modeling with View on Material Movement to and Behaviour in the Lower Head. Technical Report, CEC Project No. FI4S-CT95-0013: Investigation of Core Degradation (COBE), RUB E-193, INV-COBE(98)-D008. Ruhr-University Bochum (RUB), Department for Nuclear and New Energy Systems (NES).
11. Magallon, D., Huhtiniem, I., 1997. Corium Quenching and Spreading-The FARO Programme. Institute for Systems, Informatics and Safety. Annual Report 96, EUR 17321 EN. European Commission, Brussels, Luxembourg, pp. 52-54.
12. Maruyama Y., Yamano N., Moriyama K., Park H.S., Kudo T., Yang Y., and Sugimoto J. Quench of molten aluminium oxide associated with in-vessel debris retention by RPV internal water. In-Vessel Core Debris Retention and Coolability (NEA/CSNI/R(98)18) (1998), Nuclear Energy Agency pp. 243-250
13. Olsen C.S., Jensen S.M., Carlson E.R., and Cook B.A. Materials interactions and temperatures in the TMI-2 core. Nucl. Technol. 87 (1989) 57-94
14. Petti D.A., Adams J.P., and Anderson J.L. Analysis of fission product release behavior from the Three Mile Island Unit 2 Core. Nucl. Technol. 87 (1989) 243-263
15. Rempe J., Stickler L., Chàvez S., Thinnes G., Witt R., and Corradini M. Margin-to-failure calculations for the TMI-2 vessel. Nucl. Saf. 35 (1994) 313-326
16. Schaaf K. Uncertainty and sensitivity analysis of the heat transfer mechanisms in the lower head. In-Vessel Core Debris Retention and Coolability (NEA/CSNI/R(98)18) (1998), Nuclear Energy Agency pp. 143-153
17. Thomson K.L. Percolation cooling of the Three Mile Island Unit 2 lower head by way of thermal cracking and gap formation. Nucl. Technol. 135 (2002) 28-46
18. Wolf, J.R., Rempe, J.L., Stickler, L.A., Korth, G.E., Diercks, D.R., Neimark, L.A., Akers, D.W., Schuetz, B.K., Shearer, T.L., Chavez, S.A. Thinnes, G.L., Witt, R.J., Corradini, M.L., Kos, J.A., 1994. TMI-2 Vessel Investigation Project Integration Report. Report NUREG/CR-6197; EGG-2734. EG&G Idaho, Inc., Idaho Falls.
19. Wright R.W. Melt progression modeling implications of the TMI-2 accident. Proceedings of the Seminar on Fission Transport Processes in Reactor Accidents. Dubrovnik, Yugoslavia (1990) 833-846
20. Wright R.W. Core melt progression: status of current understanding and principal uncertainties. In: Rogers J.T. (Ed). Heat and Mass Transfer in Severe Nuclear Reactor Accidents (1996), Begell House, New York