Analysis Of Cabri-Bi1 Loss Of Flow Experiment
23RD INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2014)(2014)
摘要
The Institute for Energy and Transport (IET) in collaboration with the project partners is conducting a validation of the new severe accident analysis code for Sodium-cooled fast reactors ASTEC-Na (Accident Source Term Evaluation Code). A series of experiments performed in the past (CABRI/SCARABEE experiments) were chosen to validate the developed ASTEC-Na code.One of the in-pile experiments considered during ASTEC-Na validation phase is CABRI-BI1; loss-of-flow transient without Transient Over Power (TOP) using low burn-up MOX fuel pin. The experiment resulted in a channel voiding as a result of sodium boiling and a clad melting. Only some fuel melting took place. The results of the ASTEC-Na calculation performed within the present work were in good agreement with the steady state and the overall fuel-pin disruption behaviour, which were characterised by a thermal pin-failure mode, observed in the CABRI-BI1 experiment. This paper describes the outcome of the analysis using ASTEC-Na as well as findings for future code improvements. The main attention during validation phase was given to modelling of fuel-clad heat transfer.
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