Theoretical work on melt-coolant interactions (steam explosions)
Description
The code IVA3 is used for modelling the physical processes related to steam explosions, i.e. the premixing phase preceding the explosion as well as the explosion itself. This code has been replaced by the updated version IVA-KA in May 1994, which encompasses all model and code improvements performed till the beginning of 1994. The following further work on and with IVA-KA has been performed: 1. Inclusion of friction at inner and outer walls, improvement on the drag model, improvement of boundary conditions for outgoing flow, optional inclusion of improved water material data, improvement of the numerical procedure, correction of coding errors. 2. Three FARO-experiments (investigating the behaviour of molten material falling into water) were recalculated with IVA-KA. The time dependent pressure increase is reproduced very well for one experiment, but is not quite satisfactory for a second one. The third one cannot be simulated satisfactorily because of the presence of metallic zirconium in the melt, which is not being modelled by IVA-KA at present. 3. One PREMIX-experiment (similar to FARO, but at 1 bar ambient pressure and with smaller amounts of melt) is also being analyzed with IVA-KA. First results show a good representation of the material distribution during the penetration of the melt into the water. 4. One of the first two QUEOS-experiments performed at KfK has been simulated with IVA-KA. Some results are well reproduced by IVA-KA, but there may be a deficiency of the drag laws. (orig./HP)
Files
Additional details
Additional titles
- Original title (German)
- Theoretische Arbeiten zu Schmelze-Kuehlmittel-Wechselwirkungen (Dampfexplosionen)
Publishing Information
- Imprint Title
- Karlsruhe Research Center, Nuclear Safety Research Project (PSF). Annual report 1994
- Imprint Pagination
- 433 p.
- Journal Page Range
- p. 80-88.
- ISSN
- 0947-8620
- Report number
- FZKA--5600
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 28005581
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; EXPLOSIONS; FORSCHUNGSZENTRUM KARLSRUHE; MELTDOWN; MOLTEN METAL-WATER REACTIONS; NUMERICAL SOLUTION; PWR TYPE REACTORS; REACTOR SAFETY EXPERIMENTS; STEAM
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; GERMAN FR ORGANIZATIONS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Forschungszentrum Karlsruhe, Projekt Nukleare Sicherheitsforschung. Jahrsbericht 1994.