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 VAIDASFLORES Y FLORES ALAINGIRAULT N.LABORDE L.
Citation: ANNALS OF NUCLEAR ENERGY vol. 119 p. 427-439
Publisher: PERGAMON-ELSEVIER SCIENCE LTD
Publication Year: 2018
JRC N°: JRC106255
ISSN: 0306-4549
URI: http://publications.jrc.ec.europa.eu/repository/handle/JRC106255
DOI: 10.1016/j.anucene.2017.12.016
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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