The Proceedings of the International Conference on Nuclear Engineering (ICONE)
Online ISSN : 2424-2934
2015.23
Session ID : ICONE23-2041
Conference information
ICONE23-2041 FIRST ANALYSIS OF AGS0, LT2 AND E9 CABRI TESTS WITH THE NEW SFR SAFETY CODE ASTEC-NA
Sara Perez-MartinGiacomino BandiniVaidas MatuzasMichael BuckNathalie Girault
Author information
CONFERENCE PROCEEDINGS FREE ACCESS

Details
Abstract
Within the framework of the European JASMIN project, the ASTEC-Na code is being developed for safety analysis of severe accidents in SFR. In the first phase of validation of the ASTEC-Na fuel thermo-mechanical models three in-pile tests conducted in the CABRI experimental reactor have been selected to be analysed. We present here the preliminary results of the simulation of two Transient Over Power tests and one power ramp test (AGS0, LT2 and E9, respectively) where no pin failure occurred during the transient. We present the comparison of ASTEC-Na results against experimental data and other safety code results for the initial steady state conditions prior to the transient onset as well as for the fuel pin behaviour during the transients.
Content from these authors
© 2015 The Japan Society of Mechanical Engineers
Previous article Next article
feedback
Top