Current knowledge on core degradation phenomena, a review

Journal of Nuclear Materials

Volumn 270, Issue 1, 1999, Pages 194-211

  Hofmann, P ^a  

^a KARLSRUHE INSTITUTE OF TECHNOLOGY   (Germany)

Author keywords

[No Author keywords available]

Indexed keywords

CORE DISRUPTIVE ACCIDENTS; CORE MELTDOWN; DEGRADATION; FISSION PRODUCTS; LIGHT WATER REACTORS; LIQUEFACTION; MATHEMATICAL MODELS; MELTING; MOLTEN MATERIALS; PRESSURE VESSELS; SPENT FUELS; ZIRCONIUM ALLOYS;

CORE FLOODING; IN-VESSEL MELT RELOCATION PROCESS;

REACTOR CORES;

EID: 0032652541     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0022-3115(98)00899-X     Document Type: Review

References (40)

1. G. Van Goethem, W. Balz, E. Della Loggia, FISA-95, European Union research on severe accidents, European Union Report 16896, 1996.
2. T. Haste, B. Adroguer, U. Brockmeier, P. Hofmann, K. Müller, M. Pezzilli, In-vessel core degradation in LWR severe accidents, European Union Report 16695, 1996.
3. T. Haste, B. Adroguer, R.O. Gauntt, J.A. Martinez, L.J. Ott, J. Sugimoto, K. Trambauer, In-vessel core degradation code validation matrix, OCDE/GD (96) 14 (1996).
4. Hofmann P., Hagen S., Schanz G., Skokan A. Nucl. Technol. 87:1989;146.
5. Hobbins R.R., Petti D.A., Osetek D.J., Hagrman D.L. Nucl. Technol. 95:1991;287.
6. Hofmann P., Hagen S., Noack V., Schanz G., Sepold L. Nucl. Technol. 118:1997;200.
7. Wright R.W. Nucl. Sci. Technol. 24:1996;283.
8. Special issue on Materials interactions and temperatures in the TMI-2 core, Nuclear Technology, vol. 87/1, 1989, pp. 13-326.
9. C. Gonnier, G. Geoffroy, B. Adroguer, PHEBUS SFD programme, main results, in: ANS Proceedings, ANS Meeting, Portland, 1991, p. 76.
10. Von der Hardt P., Jones A., Lecomte C., Tattegrain A. Nucl. Safety. 35:1994;2.
11. Hofmann P., Kerwin-Peck D.K. J. Nucl. Mater. 124:1984;80.
12. Olander D.R. J. Nucl. Mater. 115:1983;271.
13. 2 fuel and oxygen between 900 and 2000°C, Experiments and PECLOX code, Kernforschungszentrum Karlsruhe report no. KfK-4422, 1988.
14. 2 by molten Zircaloy and its modeling, in: International Symposium on Severe Accidents in Nuclear Power Plants, Sorrento, Italy, March 1988.
15. Kim K.T., Olander D.R. J. Nucl. Mater. 154:1988;85.
16. P.J. Hayward, I.M. George, J. Nucl. Mater. 208 (1994) 35,43.
17. Veshchunov M.S., Hofmann P. J. Nucl. Mater. 209:1994;27.
18. Veshchunov M.S., Hofmann P., Berdyshev A.V. J. Nucl. Mater. 231:1996;1.
19. Hofmann P., Markiewicz M. J. Nucl. Mater. 209:1994;92.
20. Veshchunov M.S., Hofmann P. J. Nucl. Mater. 228:1996;318.
21. P. Hofmann, M. Markiewicz, Chemical interactions between as-received and pre-oxidized Zircaloy and stainless steel at high temperatures, Kernforschungszentrum Karlsruhe KfK-5106, 1994.
22. P. Hofmann, M. Markiewicz, Chemical interactions between as-received and pre-oxidized Zircaloy and Inconel 718 at high temperatures, Kernforschungszentrum Karlsruhe KfK-4729, 1994.
23. Hofmann P., Markiewiez M., Spino J. Nucl. Technol. 90:1990;226.
24. Veshchunov M., Hofmann P. J. Nucl. Mater. 210:1994;11.
25. Veshchunov M., Hofmann P. J. Nucl. Mater. 226:1995;72.
26. Noack V., Hagen S., Hofmann P., Schanz G., Sepold L. Nucl. Technol. 117:1997;158.
27. G. Bandini et al., Molten material relocation into the lower plenum: A status report, OECD/NEA Report (1997), NEA/CSNI/R (97) 34 (1998).
28. T. Haste, B. Adroguer, N. Aksan, C. Allison, S. Hagen, P. Hofmann, V. Noack, Degraded core quench: A status report, OECD/NEA/CSNI/R (96) 14 (1996).
29. P. Hofmann, V. Noack, M. Veshchunov et al, Physico-chemical behavior of Zircaloy fuel rod cladding tubes during LWR severe accident reflood, Forschungszentrum Karlsruhe FZKA-5846, 1997.
30. S. Hagen, P. Hofmann, V. Noack, L. Sepold, G. Schanz, Comparison of the quench experiments CORA-12, CORA-13 and CORA-17, Forschungszentrum Karlsruhe FZKA-5679, 1996.
31. Cronenberg A.W. Nucl. Technol. 97:1992;97.
32. W. Hering, P. Hofmann, Material interactions during severe LWR accidents: Summary of separate-effects test results, Kernforschungszentrum Karlsruhe KfK-5125, 1994.
33. H. Kleykamp, R. Pejsa, Chemical and X-ray diffraction analysis on selected samples from the TMI-2 reactor core, Kernforschungszentrum Karlsruhe KfK-4872, 1991.
34. S. Hagen, P. Hofmann, V. Noack, L. Sepold, G. Schanz, G. Schumacher, Cold lower end test CORA-10; Test results, Forschungszentrum Karlsruhe FZKA-5572, 1997.
35. S. Hagen, P. Hofmann, V. Noack, L. Sepold, G. Schanz, G. Schumacher, Behavior of a VVER-1000 fuel element tested under severe accident conditions in the CORA Facility; Kernforschungszentrum Karlsruhe KfK-5212, 1994.
36. 4C absorber tested under severe fuel damage conditions, Kernforschungszentrum Karlsruhe KfK-5363, 1994.
37. S.S. Abalin, V.G. Asmolov, V.D. Daragan, E.K. D'Yakov, A.V. Merzliakov, V. Yu. Vishnevsky, in: Proceedings of the 8th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Atomic Energy Soc. of Japan and the American Nuclear Soc. (ANS), Kyoto, Japan. vol. 2, 1997, pp. 581-586.
38. P. Hofmann et al., Results of the commissioning tests in the QUENCH Facility, Forschungszentrum Karlsruhe FZKA-6099, 1998.
39. P. Hofmann et al., QUENCH-01, Experimental and calculational results, Forschungszentrum Karlsruhe FZKA-6100, 1998.
40. Proceedings of the Euratom Research Framework programme 1994-1998 Nuclear Fission Safety, FISA-97 Symposium on European Union research on severe accidents, Luxembourg, 17-19 November 1997, European Union Report EUR-18258 EN, 1998.