| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 8066948 | Annals of Nuclear Energy | 2018 | 13 Pages |
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 purposes have been: BI1, E8 and EFM1, carried out in the CABRI reactor; BEâ¯+â¯3, APL1 and APL3, carried out in the SCARABEE reactor and N02, conducted in the KNS facility. ASTEC-Na has been also successfully applied (pretest calculations) to assess the performances of the KASOLA sodium loop and to verify its response under different operating conditions. Finally, a PHENIX natural circulation test has also been performed with ASTEC-Na. Besides, these experimental tests have been used as a code benchmarking exercise where thermal-hydraulic codes (CATHARE, RELAP5-Na and RELAP5-3D) and severe accident codes (SIMMER-III and SAS-SFR) have been compared with ASTEC-Na.
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Authors
G. Bandini, S. Ederli, S. Perez-Martin, M. Haselbauer, W. Pfrang, L.E. Herranz, C. Berna, V. Matuzas, A. Flores y Flores, N. Girault, L. Laborde,