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ASTEC-Na code: thermal-hydraulic model validation and benchmarking with other codes
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.G.I.4-Nuclear Reactor Safety and Emergency Preparedness
ASTEC-Na code: thermal-hydraulic model validation and benchmarking with other codes
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.G.I.4-Nuclear Reactor Safety and Emergency Preparedness
ASTEC-Na code: thermal-hydraulic model validation and benchmarking with other codes
BANDINI G. (Autor:in) / EDERLI S. (Autor:in) / PEREZ-MARTIN S. (Autor:in) / HASELBAUER M. (Autor:in) / PFRANG W. (Autor:in) / HERRANZ L. (Autor:in) / BERNA C. (Autor:in) / MATUZAS VAIDAS (Autor:in) / FLORES Y FLORES ALAIN (Autor:in) / GIRAULT N. (Autor:in)
21.03.2017
Sonstige
Elektronische Ressource
Englisch
DDC:
690
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