Development of a three-dimensional model and calculation code for the packed bed simulation for safety analyses of severe reactor accidents
Creators
- 1. Stuttgart Univ. (Germany). Inst. fuer Kernenergetik und Energiesysteme (IKE)
Description
The computer code MEWA is used for the description of severe accident sequences in light-water reactors. During the reactor accident with core disruption the solidified core fragments are displaced into the lower plenum of the reactor pressure vessel (RPV) or in case of RPV failure into the water filled reactor sump. For the progress or cessation of the severe accident the cooling of the packed bed is of main importance. With the 3D version of the code it is possible to study spatially complex packed beds with respect to their coolability. Further extension of the MEWA code will include the optimization for the improvement of the calculation efficiency and reduction of computation time. The validation will be performed by re-calculation of experiments (for instance DEBRIS experiments at the IKE) and the comparison with results of the 2D version.
Additional details
Additional titles
- Original title (German)
- Entwicklung eines dreidimensionalen Modells und Rechencodes zur Simulation von Schuettbetten fuer Sicherheitsanalysen von schweren Reaktorstoerfaellen
Publishing Information
- Imprint Title
- Annual meeting on nuclear technology 2013. Documentation
- Imprint Pagination
- 1142 p.
- Journal Page Range
- 6 p.
Conference
- Title
- Annual meeting on nuclear technology 2013
- Original Conference Title
- Jahrestagung Kerntechnik 2013
- Dates
- 14-16 May 2013
- Place
- Berlin (Germany)
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 45049778
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; COOLING; EFFICIENCY; FRAGMENTATION; M CODES; MELTDOWN; PACKED BEDS; PRESSURE VESSELS; REACTOR ACCIDENT SIMULATION; REACTOR ACCIDENTS; REACTOR CORE DISRUPTION; THREE-DIMENSIONAL CALCULATIONS; TWO-DIMENSIONAL CALCULATIONS; VALIDATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTAINERS; EVALUATION; REACTOR ACCIDENTS; SIMULATION; TESTING
Optional Information
- Notes
- Imprint:Jahrestagung Kerntechnik 2013. Dokumentation