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

This paper presents simulation results of the CABRI BI1 test using the code ASTEC-Na, currently under development, as well as a comparison of the results with available experimental data. The EU-JASMIN project (7th FP of EURATOM) centres on the development and validation of the new severe accident analysis code ASTEC-Na (Accident Source Term Evaluation Code) for sodium-cooled fast reactors whose owner and developer is IRSN. A series of experiments performed in the past (CABRI/SCARABEE experiments) and new experiments to be conducted in the new experimental sodium facility KASOLA have been chosen to validate the developed ASTEC-Na code. One of the in-pile experiments considered for the validation of ASTEC-Na thermal–hydraulic models is the CABRI BI1 test, a pure loss-of-flow transient using a low burnup MOX fuel pin. The experiment resulted in a channel voiding as a result of the flow coast-down leading to clad melting. Only some fuel melting took place. Results from the analysis of this test using SIMMER and SAS-SFR codes are also presented in this work to check their suitability for further code benchmarking purposes. 2016 The Authors. Published by Elsevier Ltd. This is an open access article under the CC BY-NC-NDlicense

FLORES Y FLORES Alain;  MATUZAS Vaidas;  PEREZ-MARTIN S.;  BANDINI G.;  EDERLI S.;  AMMIRABILE Luca;  PFRANG W.; 

2016-03-31

PERGAMON-ELSEVIER SCIENCE LTD

JRC98918

0306-4549,   

https://publications.jrc.ec.europa.eu/repository/handle/JRC98918,   

10.1016/j.anucene.2016.02.032,