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Veröffentlichungen


Hier finden Sie eine Liste mit abgeschlossenen Projekten:
Past Projects

Direct Containment Heating (DCH – DISCO)

R. Meignen, D. Plet, C. Caroli, L. Meyer, D. Wilhelm
Direct Containment Heating at low primary pressure: Experimental Investigation and multidimensional modeling
11th Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11), Avignon, France, October 2-6, 2005. NURETH11.pdf (1630kB)

L. Meyer et al.
Melt dispersion and Direct Containment Heating (DCH) Experiments in the DISCO-H Test Facility
FZKA 6988, Forschungszentrum Karlsruhe, Mai 2004. http://bibliothek.fzk.de/zb/berichte/FZKA6988.pdf

Meyer, G. Albrecht, D. Wilhelm
Direct Containment Heating Investigations for European Pressurized Water Reactors
6th International Conference on Nuclear Thermal Hydraulics, Operations and Safety (NUTHOS-6), Nara, Japan, October 4-8, 2004. (NUTHOS-6.pdf, (644kB)

L. Meyer, G. Albrecht, M. Kirstahler
Corium Dispersion and Direct Containment Heating - Experiments at Low System Pressure
10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul, Korea, October 5-9, 2003, NURETH10-M.pdf (599kB)

WILHELM D.
Recalculation of Corium Dispersion Experiments at Low System Pressure
NURETH-10, Seoul, Korea, Oct., 2003, NURETH10-W.pdf (373kB)

Meyer, L., M. Gargallo
Low Pressure Corium Dispersion Experiments with Simulant Fluids in a Scaled Annular Cavity
Nuclear Technology, 141, 257-274, March 2003,
http://www.ans.org/pubs/journals/nt/va-141-3-257-274

D. Wilhelm
Chemical Reaction Models in a Code of the SIMMER-Family
Joint IAEA/NEA Technical Meeting on the Use of Computational Fluid Dynamic Codes for Safety Analysis of Reactor Systems, Including Containment, Pisa, Italy, 11-13 November, 2002

L. Meyer, M. Greulich, M. Kirstahler, M. Schwall, E. Wachter, G. Wörner
The Test facility DISCO-H
Interner Bericht 32.21.03, Forschungszentrum Karlsruhe, IKET-Nr. 11/02, NUKLEAR: 3373, (2002), TestFacilityDISCO-H.pdf, (1511kB)

L. Meyer, M. Gargallo
Low Pressure Corium Dispersion Experiments with Lateral Failure in the Bottom Head of the Pressure Vessel
SMiRT 16 Post Conference Seminar, Containment of Nuclear Reactors, Albuquerque, New Mexico, USA, August 20-21, 2001, SMiRT16Post.pdf (1454kB)

D. Wilhelm
Extrapolation of the Thermite Dispersion Experiment SNL-Sup1 to Prototypic Conditions
SMiRT16 Post Conference Seminar, Containment of Nuclear Reactors, Albuquerque, New Mexico, USA, 2001. SMIRT2001-W.pdf (700kB)

Meyer, L., Gargallo, M.
Experiments on Melt Dispersion with lateral failure in the Bottom head of the pressure vessel
ICONE 9, Nice Acropolis – France, April 8-12, 2001, ICONE9.pdf (193kB)

M. Gargallo, L. Meyer
Experimental Simulation of Melt Dispersion at Low Pressure in an Annular Cavity
SMiRT16, Washington, DC USA, 2001. SMiRT16.pdf (700kB)

WILHELM, D.
Analysis of a thermite experiment to study low pressure corium dispersion
Wissenschaftliche Berichte, FZKA-6602 (August 2001) http://bibliothek.fzk.de/zb/berichte/FZKA6602.pdf

D. Wilhelm
Transient Code Models for Low Pressure Corium Dispersion
OECD Workshop on Ex-Vessel Debris Coolability, Karlsruhe, Germany, 15-18 November 1999. Ed. H. Alsmeyer, Forschungszentrum Karlsruhe, FZKA 6475, 2000.
OECD-1999.pdf (66kB)

Blanchat, T. K., M.M. Pilch, R.Y. Lee, L. Meyer, M. Petit
Direct Containment Heating Experiments at Low Reactor Coolant System Pressure in the Surtsey Test Facility
NUREG/CR-5746, SAND99-1634, Sandia National Laboratories, Albuquerque, N.M., (1999). NUREG-CR-5746.pdf (1831kB)

Loss of Coolant Accident (LOCA- WENKA)

M. Gargallo
Counter-current Flow Limitations in Horizontal Stratified Flows of Air and Water
FZKA 7018, Forschungszentrum Karlsruhe, Sept. 2004,
http://bibliothek.fzk.de/zb/berichte/FZKA7018.pdf

M. Gargallo, T. Schulenberg, L. Meyer, E. Laurien
Counter-Current Flow Limitations During Hot Leg Injection in Pressurized Water Reactors
Nucl. Eng. Des. 235, 785-804, 2005. Experimental Thermal and Fluid Science

T. Stäbler, L. Meyer, T. Schulenberg, E. Laurien
Investigations on Flow Reversal in Stratified Horizontal Flow
International Conference Nuclear Energy for New Europe 2005,Bled, Slovenia, September 5-8, 2005, NENE2005.pdf (390kB)