Results of the QUENCH-L2, DISCO-L2, and COMET-L2 experiments performed within the LACOMERA project at the Forschungszentrum Karlsruhe

International Conference on Nuclear Engineering, Proceedings, ICONE

Volumn 2006, Issue , 2006, Pages

  Miassoedov, Alexei ^a   Alsmeyer, Hans ^a   Meyer, Leonhard ^a   Steinbrueck, Martin ^a   Groudev, Pavlin ^b   Ivanov, Ivan ^c   Sdouz, Gert ^d  

^a KARLSRUHE INSTITUTE OF TECHNOLOGY   (Germany)

^b INSTITUTE FOR NUCLEAR RESEARCH AND NUCLEAR ENERGY   (Bulgaria)

^c TECHNICAL UNIVERSITY OF SOFIA   (Bulgaria)

^d ARC SEIBERSDORF RESEARCH GMBH   (Austria)

Author keywords

[No Author keywords available]

Indexed keywords

CORIUM CONCRETE INTERACTION; LACOMERA PROJECT; MELT FORMATION; REACTOR CAVITY;

NUCLEAR REACTOR ACCIDENTS; OXIDATION; PRESSURE VESSELS; PROJECT MANAGEMENT; REACTOR CORES; RESEARCH AND DEVELOPMENT MANAGEMENT;

NUCLEAR ENERGY;

EID: 33845766655     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1115/ICONE14-89343     Document Type: Conference Paper

References (8)

1. Miassoedov, A., et al., 2003, "Large Scale Experiments on Core Degradation, Melt Retention and Coolability (LACOMERA)", 2003, Proc. FISA-2003. EU Research in Reactor Safety, Luxembourg, November 10-13, 2003.
2. Miassoedov, A., et al., 2005, "Results of the QUENCH-L1, DISCO-L1, and COMET-L1 Experiments Performed Within the LACOMERA Project at the Forschungszentrum Karlsruhe", 2005, Proc. 13th International Conference on Nuclear Engineering (ICONE13), Beijing, China, May 16-20, 2005, CD-ROM, Paper 50607.
3. Sepold, L., et al., 2001, "Reflooding Experiments with LWR-Type Fuel Rod Simulators in the QUENCH Facility", Nuclear Engineering and Design, 204 (2001), pp.205-220.
4. Sepold, L., et al., 2004, "Hydrogen Generation in Reflooding Experiments with LWR-Type Fuel Rod Bundles (QUENCH Program)", Nuclear Technology, 147 (2004), pp. 202-215.
5. Meyer, L., et al., 2004, "Direct Containment Heating Investigations for European Pressurized Water Reactors", Proc. 6th International Conference on Nuclear Thermal Hydraulics, Operations and Safety (NUTHOS-6), Nara, Japan, October 4-8, 2004, CD-ROM, Paper N6P007.
6. Farmer, M. T., et al., 2004, "Results of Reactor Materials Experiments Investigating 2-d Core-Concrete Interaction and Debris Coolability", Proc. International Congress on Advances in Nuclear Power Plants (ICAPP '04), Pittsburgh, USA, June 13-17, 2004, CD-ROM, Paper 4102.
7. Alsmeyer, H., et al., 2005, "The COMET-LI Experiment on Long-Term Concrete Erosion and Surface Flooding", Proc. 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11), Avignon, France, October 2-6, 2005.
8. Alsmeyer, H., 1987, "BETA Experiments in Verification of the WECHSL Code: Experimental Results on the Melt-Concrete Interaction", Nuclear Engineering and Design, 103 (1987), pp. 115-125.