During a severe accident in a light water reactor, the core melts and can be relocated to the lower plenum. In these conditions the knowledge of high temperatures mechanical behavior of the lower head is fundamental in the failure time and failure mode prediction. OLHF experimentswere intended to simulate thermal/mechanical loads to which a lower head is subjected during a severe accident transient and studied its behavior. Test results were taken as reference for the validation and development of a new lower head failure model in the severe accident code SAMPSON. The OLHF facility was reproduced using the SAMPSON/DCA module (Debris Coolant Analysis). In order to test and validate the model, OLHF 1,2 and 4 experiments were simulated and the obtained results compared with the experimental ones. Calculated failure time shows a good agreement with test data even if the failure mode and location exhibit some discrepancies due to simplified assumption done in the phenomena modeling.
Nell’ ipotesi di un incidente severo con rilocazione del nocciolo la conoscenza del comportamento meccanico alle alte temperature del lower head di un reattore ad acqua leggera è di fondamentale importanza per predire tempo e modalità di fallimento. Gli esperimenti OLHF 1,2 e 4 hanno cercato di riprodurre le condizioni (pressione e temperatura) alle quali è soggetto il lower head durante un transitorio incidentale e studiarne il comportamento. I risultati ottenuti in questi esperimenti sono stati utilizzati come riferimento nello sviluppo e nella validazione del modello di fallimento del lower head del codice integrale SAMPSON per la simulazione di incidenti severi. L’ apparato sperimentale è stato riprodotto all’ interno del modulo DCA (Debris Coolant Analysis) presente in SAMPSON. Al fine di testare e validare il modello sono state effettuate diverse simulazioni e i risultati ottenuti confrontati con quelli sperimentali. I tempi di fallimento sono stati ben riprodotti in tutte le simulazioni anche se le modalità e la posizione della rottura presentano delle incongruenze dovute alle assunzioni semplificative adottate durante la modellizzazione dei fenomeni.
Numerical investigation of light water reactor lower head failure under severe accident conditions using the SAMPSON code
SCARPA, FILIPPO
2014/2015
Abstract
During a severe accident in a light water reactor, the core melts and can be relocated to the lower plenum. In these conditions the knowledge of high temperatures mechanical behavior of the lower head is fundamental in the failure time and failure mode prediction. OLHF experimentswere intended to simulate thermal/mechanical loads to which a lower head is subjected during a severe accident transient and studied its behavior. Test results were taken as reference for the validation and development of a new lower head failure model in the severe accident code SAMPSON. The OLHF facility was reproduced using the SAMPSON/DCA module (Debris Coolant Analysis). In order to test and validate the model, OLHF 1,2 and 4 experiments were simulated and the obtained results compared with the experimental ones. Calculated failure time shows a good agreement with test data even if the failure mode and location exhibit some discrepancies due to simplified assumption done in the phenomena modeling.| File | Dimensione | Formato | |
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https://hdl.handle.net/10589/120781