Facility Description: Phébus facility at Cadarache operated by ASNR and CEA - simulating nuclear reactor accidents to study core melt behavior and fission product release.
Test Identification: FPT-0
SA-Related Topics / Phenomena: FP depletion to surfaces under condensing conditions (non-soluble)Measured Parameters: T, p, r.H., Gas conc., FP concentrationn and discrimination, hydrogen, iodine
Modelling: Radioactive materials exiting the bundle were conveyed through a hot line trace-heated at 970 K to a steam generator simulated by a single inverted U-tube (scaling ratio 1/5000 for the number of tubes) and then to model containment through a cold leg trace-heated at 420 K
Simulation Code: AC2, COCOSYS, ASTEC, MELCOR, MAAP
Experimental Research Program: Phébus
Link to PIRT: WP-1.5 ST-15
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Facility Description: Phébus facility at Cadarache operated by ASNR and CEA - simulating nuclear reactor accidents to study core melt behavior and fission product release.
Test Identification: FPT-1
SA-Related Topics / Phenomena: FP depletion to surfaces under condensing conditions (non-soluble)Measured Parameters: T, p, r.H., Gas conc., FP concentrationn and discrimination, hydrogen, iodine
Modelling: Radioactive materials exiting the bundle were conveyed through a hot line trace-heated at 970 K to a steam generator simulated by a single inverted U-tube (scaling ratio 1/5000 for the number of tubes) and then to model containment through a cold leg trace-heated at 420 K
Simulation Code: AC2, COCOSYS, ASTEC, MELCOR, MAAP
Experimental Research Program: Phébus
Link to PIRT: WP-1.5 ST-15
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References: [1] R. Dubourg, H. Faure-Geors, G. Nicaise, M. Barrachin, Fission product release in the first two PHEBUS tests FPT0 and FPT1, Nuclear Engineering and Design, Volume 235, Issue 20, 2005, Pages 2183-2208, ISSN 0029-5493,
https://doi.org/10.1016/j.nucengdes.2005.03.007 ,
https://doi.org/10.1016/j.anucene.2013.03.037Contributed By: ???