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|Title:||ASTEC-Na code: thermal-hydraulic model validation and benchmarking with other codes|
|Authors:||BANDINI G.; EDERLI S.; PEREZ-MARTIN S.; HASELBAUER M.; PFRANG W.; HERRANZ L.; BERNA C.; MATUZAS VAIDAS; FLORES Y FLORES ALAIN; GIRAULT N.; LABORDE L.|
|Citation:||ANNALS OF NUCLEAR ENERGY vol. 119 p. 427-439|
|Publisher:||PERGAMON-ELSEVIER SCIENCE LTD|
|Type:||Articles in periodicals and books|
|Abstract:||This paper describes the work performed within the WP2.1 of the JASMIN project to validate the thermal-hydraulic models of ASTEC-Na code. The experiments used for validation purpose have been: BI1, E8 and EFM1, carried out in the CABRI reactor, BE+3, APL1 and APL3, carried out in the SCARABEE reactor and N02, conducted in the KNS facility. Moreover, the simulation of CABRI and SCARABEE tests has been the object of a code benchmark exercise. Thermal-hydraulic codes such as CATHARE, RELAP5-Na and RELAP5-3D as well as severe accident codes such as SIMMER-III and SAS-SFR have been used as benchmark to assess the ASTEC-Na performances. ASTEC-Na has been also successfully applied (pretest calculations) to assess the performances of the KASOLA sodium loop and verify its response under different operating conditions. Also in this case, the ASTEC-Na results have been bench marked with other thermal-hydraulic system codes (CATHARE, RELAP5-3D and RELAP5-Na).|
|JRC Directorate:||Nuclear Safety and Security|
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