Analysis of ASTEC-Na capabilities for simulating a loss of flow CABRI experiment

• DOI: 10.1016/j.anucene.2016.02.032
• Publication Date: 2016-03-16T16:54:06Z
• Authors: A. Flores y Flores; V. Matuzas; S. Perez-Martin; G. Bandini; S. Ederli; L. Ammirabile; W. Pfrang
• Keywords: Thermal hydraulics

This paper presents simulation results of the CABRI BI1 test using code ASTEC-Na, currently under development, as well a comparison with available experimental data. The EU-JASMIN project (7th FP EURATOM) centres on development and validation new severe accident analysis ASTEC-Na (Accident Source Term Evaluation Code) for sodium-cooled fast reactors whose owner developer is IRSN. A series experiments performed in past (CABRI/SCARABEE experiments) to be conducted sodium facility KASOLA have been chosen validate developed code. One in-pile considered thermal–hydraulic models test, pure loss-of-flow transient low burnup MOX fuel pin. experiment resulted channel voiding result flow coast-down leading clad melting. Only some melting took place. Results from this SIMMER SAS-SFR codes are also presented work check their suitability further benchmarking purposes.