SADD - Severe accident database directory

Molten Corium Concrete Interaction- (MCCI) (4)

Test Identification: VP-U1 & VP-U3
SA-Related Topics / Phenomena: Prototypic corium slow solidification
Measured Parameters: Composition, Temperature
Modelling: Thermodynamic modelling,
Simulation Code: NUCLEA, TAF-ID
Experimental Research Program: EURATOM project ECOSTAR

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References: C. Journeau, C. Jégou, J. Monerris, P. Piluso, K. Frolov, Phase Macrosegregation during the slow solidification of prototypic corium, 10th Int Conf Nucl React. Thermalhydraulics, NURETH10, Seoul, Korea, 2003.
Comments:
Contributed By: C. Journeau
IP/Copyright Situation:

Test Identification: VB-U4 and VB-U5
SA-Related Topics / Phenomena: Molten Core Concrete Interaction
Measured Parameters: Temperature, injected power, concrete ablation,
Modelling: 2D MCCI (oxidic corium/siliceous concrete)
Simulation Code: TOLBIAC-ICB, ASTEC/MEDICIS, COSACO, CORQUENCH, WECHSL, CORIUM-2D
Experimental Research Program: EURATOM project SARNET French national program CEA, IRSN, EDF

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References: C. Journeau, P. Piluso, J.F. Haquet, E. Boccaccio, V. Saldo, J.M. Bonnet, S. Malaval, L . Carénini, L. Brissonneau (2009), Two dimensional interactions of corium with concretes: The VULCANO VB Test series, Ann. Nucl. Ener. 36 :1597-1613.
Comments: Confirmed anisotropic ablation of siliceous concrete (with two prototypic corium compositions). VB-U5 used for a European benchmark
Contributed By: C. Journeau
IP/Copyright Situation: to be discussed

Test Identification: VB-U6
SA-Related Topics / Phenomena: Molten Core Concrete Interaction
Measured Parameters: Temperature, injected power, concrete ablation,
Modelling: 2D MCCI (oxidic corium/limestone concrete)
Simulation Code: TOLBIAC-ICB
Experimental Research Program: EURATOM project SARNET French national program CEA, IRSN, EDF

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References: C. Journeau, P. Piluso, J.F. Haquet, E. Boccaccio, V. Saldo, J.M. Bonnet, S. Malaval, L . Carénini, L. Brissonneau (2009), Two dimensional interactions of corium with concretes: The VULCANO VB Test series, Ann. Nucl. Ener. 36 :1597-1613.
Comments: Confirmed isotropic ablation of limestone concrete. Used for an European benchmark
Contributed By: C. Journeau
IP/Copyright Situation: to be discussed

Test Identification: VB-U7
SA-Related Topics / Phenomena: Molten Core Concrete Interaction
Measured Parameters: Temperature, injected power, concrete ablation,
Modelling: 2D MCCI (oxidic corium/EPR sacrificial -ferrosiliceous- concrete)
Simulation Code: TOLBIAC-ICB
Experimental Research Program: EURATOM project "PLINIUS-FP6"

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References: T. Sevón, C. Journeau, L. Ferry, VULCANO VB-U7 experiment on interaction between oxidic corium and hematite-containing concrete, Ann. Nucl. Ener. 59, 224-229, 2013. C. Journeau, P. Piluso, P. Correggio, L. Ferry, G. Fritz, J.F. Haquet, J. Monerris, J.M. Ruggieri, M. Sanchez-Brusset, C. Parga, Contributions of the VULCANO experimental programme to the understanding of MCCI phenomena, Nuclear Engineering and Technology, 44(2012), 261-272.
Comments: Using sacrificial concrete materials from Olkiluoto concrete station
Contributed By: C. Journeau
IP/Copyright Situation:

SPREADING- (SG) (4)

Test Identification: VE-U7
SA-Related Topics / Phenomena: Corium Spreading
Measured Parameters: Spread progression temperatures
Modelling: Spreading of prototypic corium over ceramic and concrete channels
Simulation Code: THEMA, CORFLOW, LAVA, MPS, MPH
Experimental Research Program: EURATOM project ECOSTAR

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References: C. Journeau, J.F. Haquet, B. Spindler, C. Spengler, J. Foit, "The Vulcano VEU7 Corium Spreading Benchmark", Progr. Nucl. Ener. , 48, 215-234 (2006).

Jubaidah et al., Investigation on corium spreading over ceramic and concrete substrates in VULCANO VE-U7 experiment with moving particle semi-implicit method, Ann. Nucl. Ener. 141: 107266 (2020).
Comments: Used for an European benchmark
Contributed By: C. Journeau
IP/Copyright Situation: Open to European partners

Test Identification: VE-U1, VE-U3, VE-U5
SA-Related Topics / Phenomena: Corium Spreading
Measured Parameters: Spread progression temperatures
Modelling: Spreading of prototypic corium
Simulation Code: THEMA
Experimental Research Program: EURATOM projects CSC and ECOSTAR + IPSN sponsorship of some tests

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References: C. Journeau, E. Boccaccio, C. Brayer, G. Cognet, J.F. Haquet, C. Jégou, P. Piluso, J. Monerris, Ex-vessel corium spreading : results from the VULCANO spreading tests, Nucl. Eng. Design, 223: 75-102, 2003.
https://www.sciencedirect.com/science/article/pii/S0029549302003977

G. Cognet, et al, “Corium spreading and coolability: CSC Project”, Nuclear Engineering and Design, Volume 209, Issues 1-3, November 2001, pages 127-138
https://www.sciencedirect.com/science/article/pii/S0029549301003958
Comments:
Contributed By: C. Journeau T. Keim/M. Fischer
IP/Copyright Situation: TBD

Test Identification: VE-U8
SA-Related Topics / Phenomena: Corium Spreading
Measured Parameters: Spread progression temperatures
Modelling: Spreading of (U,Zr)O2
Simulation Code: THEMA, MPS
Experimental Research Program: EURATOM project ECOSTAR + IRSN funding

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References: C. Journeau, E. Boccaccio, P. Fouquart, C. Jégou, P. Piluso, Corium spreading over concrete: The VULCANO VE-U7 and VE-U8 tests, 10th Int Conf. Nucl. Eng., ICONE 10, Arlington, VA, 2002.
Jubaidah et al., 2D MPS method analysis of ECOKATS-V1 spreading with crust fracture model, Nucl. Eng. Des. 379: 111251 (2021)
Comments:
Contributed By: C. Journeau
IP/Copyright Situation: To be discussed

Test Identification: VE-U9
SA-Related Topics / Phenomena: Corium Spreading
Measured Parameters: Spread progression temperatures
Modelling: Spreading of prototypic corium over ceramic and concrete channels ; influence of slip-no slip condition on sacrificial concrete
Simulation Code: MPH;
Experimental Research Program: Mitsubishi Heavy Industry funding

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References: M. Johnson, A. Denoix, V. Bouyer, H. Goda, S. Kamohara, J. Takeuchi, L. Brissonneau, C. Journeau, High-temperature ex-vessel corium spreading. Part 1: experimental investigations on ceramic and sacrificial concrete substrates, J. Nucl. Sci. Tech. (2021) 59: 446-458 & 82. M. Johnson, T. Schiano, A. Denoix, V. Bouyer, C. Journeau, High-temperature ex-vessel corium spreading. Part 2: scaling principles for gravity-viscous spreading with slip at the melt surface interface, J. Nucl. Sci. Tech. (2021) 59: 459-471.
R. Yokoyama, M. Kondo, S. Suzuki, M. Johnson, S. Miwa, M. Pellegrini, A. Denoix, V. Bouyer, C. Journeau, K. Okamoto, A Lagrangian approach to ex-vessel corium spreading over ceramic and concrete substrates using moving particle hydrodynamics, Nucl. Eng. Des. 399: 112029, 2022.
Comments:
Contributed By: C. Journeau
IP/Copyright Situation: To be discussed with MHI

Facility Details: VULCANO