Assessment of the severe accident mitigation features of the European pressurized water reactor by cooperative research and development

Nuclear Technology

Volumn 126, Issue 2, 1999, Pages 143-152

  Eglin, Wolfgang ^a   Krugmann, Ulrich ^b   Weisshäupl, Horst A ^c   Scholtyssek, Werner ^d  

^a EnBW Kraftwerke AG   (Germany)

^b SIEMENS AG   (Germany)

^c JOINT RESEARCH CENTRE   (Italy)

^d KARLSRUHE INSTITUTE OF TECHNOLOGY   (Germany)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; CORE MELTDOWN; RESEARCH AND DEVELOPMENT MANAGEMENT;

SEVERE ACCIDENT PHENOMENA;

PRESSURIZED WATER REACTORS;

EID: 0032677824     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT99-A2963     Document Type: Article

References (11)

1. B. KUCZERA, W. EGLIN, and H. WEISSHÄUPL, "Cooperative R&D Work on LWR Severe Accident Phenomena," Proc. Int. Topl. Mtg. Advanced Reactors Safety, Pittsburgh, Pennsylvania, April 17-21, 1994, Vol. 1, p. 559, American Nuclear Society (1994).
2. L. MEYER et al., "Investigation of the Premixing Phase of a Steam Explosion with Hot Spheres," Proc. Int. Mtg. Advanced Reactors Safety, Orlando, Florida, June 1-5, 1997, Vol. 1, p. 503, American Nuclear Society (1997).
3. F. DUPLAT et al., "Recent Results on the BILLEAU Pre-mixing Experiment Using Cold and Hot Spheres (2200 K) and Comparisons with MC3D Calculations," Proc. Int. Mtg. Advanced Reactors Safety, Orlando, Florida, June 1-5, 1997, Vol. 1, p. 529, American Nuclear Society (1997).
4. W. SCHÜTZ et al., "PREMIX, An Experimental Approach to Investigate the Mixing Behaviour of a Hot Melt Being Poured into Water," Proc. Int. Mtg. Advanced Reactors Safety, Orlando, Florida, June 1-5, 1997, Vol. 2, p. 887, American Nuclear Society (1997).
5. R. KRIEG et al., "Mechanical Behaviour of the Reactor Vessel During an In-Vessel Steam Explosion," Proc. Conf. European Pressurized Water Reactor-EPR, Cologne, Germany, October 19-21, 1997.
6. W. HERING et al., "Current FZK-Investigation on Core Degradation," Proc. Conf. European Pressurized Water Reactor-EPR, Cologne, Germany, October 19-21, 1997.
7. W. BREITUNG and P. ROYL, "FZK Results on Hydrogen Behaviour and Mitigation in Severe PWR Accidents," Proc. Conf. European Pressurized Water Reactor-EPR, Cologne, Germany, October 19-21, 1997.
8. P. ROYL et al., "Simulation of Hydrogen Transport with Mitigation Using the 3D Field Code GASFLOW," Proc. Int. Mtg. Advanced Reactors Safety, Orlando, Florida, June 1-5, 1997, Vol. 1, p. 578, American Nuclear Society (1997).
9. G. FIEG et al., "Simulation Experiments on the Spreading Behaviour of Molten Core Melts," Proc. National Heat Transfer Conf., Houston, Texas. August 3-6, 1996, American Nuclear Society (1996).
10. W. STEINWARZ et al., "COMAS-Großmaßstäbliche Experimente zum Verhalten von Kernschmelzen außerhalb des Reaktordruckbehälters," presented at Jahrestagung Kerntechnik'96, Mannheim, Germany, May 1996.
11. W. TROMM et al., "Experiments and Theoretical Modelling for a Core Catcher Concept for Future Light Water Reactors," AIChE Symp. Ser., 92, 304 (1996).