SADD - Severe accident database directory

Focus area 2: Fission product chemistry, transport and remobilization behaviour in RCS (2)

Facility Description: Scale 1/5000th of a 900 Mwe PWR
Test Identification: FPT0, FPT1, FPT2 tests
SA-Related Topics / Phenomena:
Measured Parameters: Nature of the coolant (steam-rich or steam-poor) given by different steam flow rate. Material composition of the control rod (Ag-In-Cd or B4C). Sump pH and thermal-hydraulic conditions imposed (evaporating or not)
Modelling: Fuel temperature (350-3100°C), cumulated hydrogen production (0 - 0.12 kg), molten mass (0 - 2.0 kg), caesium and iodine relative release from the core, caesium and iodine relative released mass into the containment , iodine aerosol concentration (0 - 0.1 g/m3), iodine absorved on wet condenser (0 - 0.001 mol)
Simulation Code: ATHLET-CD COCOSYS ASTEC/IODE IMPAIR3-JRC INSPECT MELCOR SCDAP/RELAP5 ICARE2 ASTEC/SOPHAEROS
Experimental Research Program: PHEBUS FP Programme
Link to PIRT: ST12, ST13, ST16

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References: [1] B. Clément, R. Zeyen, «The objectives of the Phébus FP experimental programme and main findings», Annals of Nuclear Energy, Volume 61,
2013, Pages 4-10, https://doi.org/10.1016/j.anucene.2013.03.037.
[2] L. Tiborcz, S. Beck, «Uncertainty and sensitivity analysis of the fission product behaviour in the Phébus FPT1 test with the system code AC2», Nuclear Engineering and Design, Volume 429, 2024, 113594, https://doi.org/10.1016/j.nucengdes.2024.113594.
[3] N. Girault et al., «LWR severe accident simulation: Iodine behaviour in FPT2 experiment and advances on containment iodine chemistry», Nuclear Engineering and Design, Volume 243, 2012, Pages 371-392, https://doi.org/10.1016/j.nucengdes.2011.11.011.
[4] K. Mueller et al., «Final interpretation report of the PHEBUS test FPT0 (bundle aspects)», DG JRC Institute for energy, October 2007.
[5] N. Girault et al., Towards a better understanding of iodine chemistry in RCS of nuclear reactors, Nuclear Engineering and Design 239 (2009) 1162–1170. doi:10.1016/j.nucengdes.2009.02.008
[6] FPT0, FPT1 and FPT2 final reports.
[7] Cousin et al. Modelling of fission-product transport in the reactor coolant system. Annals of Nuclear Energy 61 (2013) 135–142. https://doi.org/10.1016/j.anucene.2013.02.035
[8] B. Xerri et al., «Ab initio calculations and iodine kinetic modeling in the reactor coolant system of a pressurized water reactor in case of severe nuclear accident», Computational and Theoretical Chemistry,
Volume 990, Pages 194-208, 2012, https://doi.org/10.1016/j.comptc.2012.02.024

Facility Description: Scale 1/5000th of a 900 Mwe PWR
Test Identification: FPT3 tests
SA-Related Topics / Phenomena:
Measured Parameters: Nature of the coolant (steam-rich or steam-poor) given by different steam flow rate. Material composition of the control rod (Ag-In-Cd or B4C). Sump pH and thermal-hydraulic conditions imposed (evaporating or not)
Modelling: Bundle temperature from initial to final state (500 - 3000K), core power (0 - 4 MW), H2 mass flow rate (0.0-0.06 g/s), H2 total mass released (0 - 130 g), boron release from bundle (in percentage units), CO total mass production (0-40 g), CO2 total mass production (0-25 g), iodine release from bundle (in percentage units), caesium release from bundle (in percentage units), molybdenum release from bundle (in percentage units), overall mass retention (0-8000 mg depending on type), condensation rate (0-1 g/s), total aerosol airborne mass in the containment (0 - 55 g), iodine mass deposited on painted surfaces (0-350 mg)
Simulation Code: ASTEC MAAP MELCOR ATHLET/COCOSYS ATHLET-CD COCOSYS ASTEC INSPECT2k/IODAIR-v3 ECART
Experimental Research Program: PHEBUS FP Programme
Link to PIRT: ST12, ST13, ST16

Show/Hide Additional Details ▼

References: [1] B. Clément, R. Zeyen, «The objectives of the Phébus FP experimental programme and main findings», Annals of Nuclear Energy, Volume 61,
2013, Pages 4-10, https://doi.org/10.1016/j.anucene.2013.03.037.
[2] M. Di Giul et al., «SARNET benchmark on Phébus FPT3 integral experiment on core degradation and fission product behaviour», Annals of Nuclear Energy,
Volume 93, 2016, Pages 65-82, https://doi.org/10.1016/j.anucene.2016.01.046.
[3] T. Haste et al., Study of boron behaviour in the primary circuit of water reactors under severe accident conditions: A comparison of Phebus FPT3 results with other recent integral and separate-effects data, NED 246, p. 147-156, 2012.
[4] B. Clement and R. Zeyen, «The Phebus Fission Product and Source Term International Programmes», International Conference Nuclear Energy for New Europe 2005, Nuclear Society of Slovenia, 2005.

Facility Details: PHEBUS FP