Organization / Localization: IRSN Country: France Test Identification: FPT-0 SA-Related Topics / Phenomena:Investigate in-pile the late phase of core degradation and FP release (volatile and non-volatile). Measured Parameters: 1. Melt progression and fission product (FP) release in steam-rich environment2. FP chemistry and deposits in non condensing steam generator 3.Aerosol deposition, Iodine radiochemistry at pH5 Simulation Code: ASTEC, ATHLET-CD/COCOSYS, IMPACT/SAMPSON, MAAP-EDF4.04, MELCOR, RELAP/SCDAP, SCDAPSIM
References: Hanniet-Girault N and Repetto G, "FPT0 Final Report - Final Version", IPSN/DRS/SEA report SEA 1/99 (1999) IP/Copyright Situation: To be checked
References: FPT-1: Quick Look Report (1996), Preliminary Report (1997) IP/Copyright Situation: To be checked
Organization / Localization: IRSN Country: France Test Identification: FPT-2 SA-Related Topics / Phenomena:Investigate in-pile the late phase of core degradation and FP release (volatile and non-volatile). Measured Parameters: 1. As FPT-1 under steam poor conditions 2.As FPT-1 with effect of boric acid in the steam 3.Evaporating sump at pH9 Simulation Code: ASTEC, ATHLET-CD/COCOSYS, IMPACT/SAMPSON, MAAP-EDF4.04, MELCOR, RELAP/SCDAP, SCDAPSIM
References: Von der Hardt P and Tattegrain A, "The PHEBUS Fission Product Project", Journal of Nuclear Materials 188 (1992) IP/Copyright Situation: To be checked
References: Von der Hardt P and Tattegrain A, "The PHEBUS Fission Product Project", Journal of Nuclear Materials 188 (1992) IP/Copyright Situation: To be checked
References: Von der Hardt P and Tattegrain A, "The PHEBUS Fission Product Project", Journal of Nuclear Materials 188 (1992) IP/Copyright Situation: To be checked
Organization / Localization: ASNR/CEA Country: France Facility Description: Phébus facility at Cadarache operated by ASNR and CEA - simulating nuclear reactor accidents to study core melt behavior and fission product release. Facility Status: closed 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
Organization / Localization: ASNR/CEA Country: France Facility Description: Phébus facility at Cadarache operated by ASNR and CEA - simulating nuclear reactor accidents to study core melt behavior and fission product release. Facility Status: closed 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