In-Vessel Melt Retention Severe Accident Management Strategy for Existing and Future NPPs

Informations projet

IVMR

N° de convention de subvention: 662157

DOI 10.3030/662157

Projet clôturé

Date de signature de la CE 20 Mai 2015

Date de début 1 Juin 2015

Date de fin 30 Novembre 2019

Financé au titre de

• Euratom

Coût total € 8 262 989,38

Contribution de l’UE € 4 831 454,00

Coordonné par

INSTITUT DE RADIOPROTECTION ET DE SURETE NUCLEAIRE
France

CORDIS fournit des liens vers les livrables publics et les publications des projets HORIZON.

Les liens vers les livrables et les publications des projets du 7e PC, ainsi que les liens vers certains types de résultats spécifiques tels que les jeux de données et les logiciels, sont récupérés dynamiquement sur OpenAIRE .

Livrables

Documents, rapports (34)

Report on mechanical resistance

Synthesis report on task 2.4 about the mechanical resistance of ablated wall under high heat flux

Methodology - Synthesis

Synthesis report about the updated methodology for demonstration of In-Vessel melt retention

Final report on simulant stratified pool

Interim report on heat transfer within stratified molten pool with simulant materials, performed at KTH (POMECO facility)

3rd periodic report

Summary of activities and main results obtained during the third year of the project

Review of baffling of the vessel

Final report on baffling of the vessel (design, efficiency, optimization)

Final report on critical scenarios

Final report on task 5.1 – Options to reduce the probability of critical scenarios

Final project report

Summary of activities and main results obtained during the whole project

2nd periodic report

Summary of activities and main results obtained during the second year of the project

Final report on top cooling

Final report on direct cooling of the top metal layer performed in KTH facility

Review of alternative innovations

Synthesis report on benefits of several innovations to improve IVMR success

Final report on melt properties

Final report on melt properties measurements performed in CEA facilities

Influence of oxidation and fluid properties on boiling and CHF: Results of the CNU-M1 and ANUBIS tests
Report on CERES tests

Final report on complementary experiments on the CERES facilities (MTA-EK)

Report on the use of CFD

Synthesis report on task 2.3 about the use of CFD for simulation of stratified molten pool or external cooling.

Minutes of the kick-off meeting

Summary of initial discussions and presentations about the objectives of the project and the contributions of participants.

Report on modelling

Synthesis report on task 2.2 about modelling and improvement of codes

Synthesis report on spray cooling

Synthesis report on RPV spray cooling for IVMR and recommendations for system design.

Final report on oxide conductivity

Final report on measurements of heat conductivity of the solid oxide phase performed in ITU facility

Synthesis report on corium pool behaviour

Final report on physicochemical phenomena in corium debris and molten pool

Final report on innovations
Preliminary report on spray cooling

State-of-the-art review of spray cooling and heat transfer models and feasibility study report

Review of instrumentation for SAMG

Final report on instrumention to monitor the IVMR management

First periodic report

Summary of activities and main results obtained during the first year of the project

Communication action Plan

Communication action Plan (CAP)

Review of spray cooling

Final report on spray cooling (existing options, design, efficiency)

Final report on core reflood

Final report on the effect of core re-flood

Results of the PIRT on phenomena relevant for IVR modelling

Description of the method to establish the rankings and conclusions of the ranking

Final report on full scale tests

Final report on full scale geometry tests (2D slice) performed at UJV

Report on experimental study of spray cooling

Synthesis report on experimental study of CHF and post dry heat transfer with spray water cooling of downward inclined vessel steel surface (performed at KTH)

Review of vessel coating

Final report on the efficiency of various vessel coatings

Final report on core debris coolability

Final report on the effect of partially melted debris re-flood performed in PEAL and PRELUDE facilities (IRSN)

Final report on the large scale cold-crucible experiment

Final report on the measurements of heat flux between the vessel wall and the stratified molten pool performed in the large scale cold-crucible experiment at CVR

Final report on small scale tests

Final report of small scale experimental results performed at UJV

Review of active passive/injection systems

Final report on the review of active/passive in-vessel injection systems

Démonstrateurs, pilotes, prototypes (1)

IVMR website

Creation of IVMR website

Publications

Articles approuvés par les pairs (15)

Some considerations to improve the methodology to assess In-Vessel Retention strategy for high-power reactors

Auteurs: F. Fichot, L. Carénini, M. Sangiorgi, S. Hermsmeyer, A. Miassoedov, S. Bechta, J. Zdarek, D. Guenadou
Publié dans: Annals of Nuclear Energy, Numéro 119, 2018, Page(s) 36-45, ISSN 0306-4549
Éditeur: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2018.03.040

Plant application of ICARE/ASTECv2.0r3 computer code for investigation of in-vessel melt retention in VVER-1000 reactor design

Auteurs: R. Gencheva, A. Stefanova, P. Groudev
Publié dans: Annals of Nuclear Energy, Numéro 81, 2015, Page(s) 207-212, ISSN 0306-4549
Éditeur: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2015.02.039

Modelling issues related to molten pool behaviour in case of In-Vessel Retention strategy

Auteurs: L. Carénini, F. Fichot, N. Seignour
Publié dans: Annals of Nuclear Energy, Numéro 118, 2018, Page(s) 363-374, ISSN 0306-4549
Éditeur: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2018.04.032

Study of in-vessel melt retention for VVER-1000/v320 reactor

Auteurs: R. Gencheva, A. Stefanova, P. Groudev, B. Chatterjee, D. Mukhopadhyay
Publié dans: Nuclear Engineering and Design, Numéro 298, 2016, Page(s) 208-217, ISSN 0029-5493
Éditeur: Elsevier BV
DOI: 10.1016/j.nucengdes.2015.12.031

Past and Future Research at IRSN on Corium Progression and Related Mitigation Strategies in a Severe Accident

Auteurs: Didier Jacquemain, Didier Vola, Renaud Meignen, Jean-Michel Bonnet, Florian Fichot, Emmanuel Raimond, Marc Barrachin
Publié dans: Nuclear Technology, Numéro 196/2, 2016, Page(s) 161-174, ISSN 0029-5450
Éditeur: American Nuclear Society
DOI: 10.13182/NT16-13

Adoption of in-vessel retention concept for VVER-440/V213 reactors in Central European Countries

Auteurs: Peter Matejovic, Miroslav Barnak, Milan Bachraty, Lubomir Vranka, Robert Berky
Publié dans: Nuclear Engineering and Design, Numéro 314, 2017, Page(s) 93-109, ISSN 0029-5493
Éditeur: Elsevier BV
DOI: 10.1016/j.nucengdes.2017.01.015

Towards the accurate numerical prediction of thermal hydraulic phenomena in corium pools

Auteurs: Afaque Shams
Publié dans: Annals of Nuclear Energy, Numéro 117, 2018, Page(s) 234-246, ISSN 0306-4549
Éditeur: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2018.03.031

Modelling of Severe Accident and In-Vessel Melt Retention Possibilities in BWR Type Reactor

Auteurs: Mindaugas Valinčius, Tadas Kaliatka, Algirdas Kaliatka, Eugenijus Ušpuras
Publié dans: Science and Technology of Nuclear Installations, Numéro 2018, 2018, Page(s) 1-14, ISSN 1687-6075
Éditeur: Hindawi Publishing Corporation
DOI: 10.1155/2018/7162387

Thermophysical properties of U, Zr-oxides as prototypic corium materials

Auteurs: Alice Seibert, Dragos Staicu, David Bottomley, Marco Cologna, Jacobus Boshoven, Herwin Hein, Emthetal Kassim, Sarah Nourry, Markus Ernstberger, Davide Robba, Rudy Konings
Publié dans: Journal of Nuclear Materials, Numéro 520, 2019, Page(s) 165-177, ISSN 0022-3115
Éditeur: Elsevier BV
DOI: 10.1016/j.jnucmat.2019.04.019

Experiments on interactions of molten steel with suboxidized corium crust for in-vessel melt retention

Auteurs: Adrien Pivano, Pascal Piluso, Nourdine Chikhi, Jules Delacroix, Pascal Fouquart, Romain Le Tellier
Publié dans: Nuclear Engineering and Design, Numéro 355, 2019, Page(s) 110271, ISSN 0029-5493
Éditeur: Elsevier BV
DOI: 10.1016/j.nucengdes.2019.110271

Measurement of Type 304L Stainless Steel and 16MND5 Ferritic Steel Density and Surface Tension: Possible Impact for Stratified Molten Pool

Auteurs: N. Chikhi, P. Fouquart, J. Delacroix, P. Piluso
Publié dans: Nuclear Technology, Numéro 205/1-2, 2018, Page(s) 200-212, ISSN 0029-5450
Éditeur: American Nuclear Society
DOI: 10.1080/00295450.2018.1486160

Main outcomes from the IVR code benchmark performed in the European IVMR project

Auteurs: L. Carénini, F. Fichot, N. Bakouta, A. Filippov, R. Le Tellier, L. Viot, I. Melnikov, P. Pandazis
Publié dans: Annals of Nuclear Energy, Numéro 146, 2020, Page(s) 107612, ISSN 0306-4549
Éditeur: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2020.107612

Experimental Studies on Two-Layer Corium Heat Transfer in Light Water Reactor Lower Head in LIVE2D Facility

Auteurs: Xiaoyang Gaus-Liu, Thomas Cron, Beatrix Fluhrer
Publié dans: Nuclear Technology, 2020, Page(s) 1-12, ISSN 0029-5450
Éditeur: American Nuclear Society
DOI: 10.1080/00295450.2020.1743102

Elaboration of a Phenomena Identification Ranking Table (PIRT) for the modelling of In-Vessel Retention

Auteurs: F. Fichot, L. Carénini, N. Bakouta, H. Esmaili, L. Humphries, T. Laato, R. Le Tellier, L. Saas, I. Melnikov, P. Pandazis, S. Weber, R.J. Park, A. Filippov, V. Strizhov
Publié dans: Annals of Nuclear Energy, Numéro 146, 2020, Page(s) 107617, ISSN 0306-4549
Éditeur: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2020.107617

A simplified model for the quaternary U-Zr-Fe-O system in the miscibility gap

Auteurs: Shambhavi Nandan, Florian Fichot, Bruno Piar
Publié dans: Nuclear Engineering and Design, Numéro 364, 2020, Page(s) 110608, ISSN 0029-5493
Éditeur: Elsevier BV
DOI: 10.1016/j.nucengdes.2020.110608

Actes de conférence (4)

The Impact of Transient Behavior of Corium in the Lower Head of a Reactor Vessel for In-Vessel Melt Retention Strategies

Auteurs: L. Carénini, F. Fichot
Publié dans: Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, 2016, Page(s) V004T13A009, ISBN 978-0-7918-5004-6
Éditeur: ASME
DOI: 10.1115/ICONE24-60598

A Revised Methodology to Assess In-Vessel Retention Strategy for High-Power Reactors

Auteurs: F. Fichot, L. Carénini, W. Villanueva, S. Bechta
Publié dans: Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, 2018, Page(s) V007T11A014, ISBN 978-0-7918-5151-7
Éditeur: ASME
DOI: 10.1115/icone26-82248

Numerical Simulation of Induction Heating for Molten Pool Heat Transfer Experiments in Slice Geometry

Auteurs: D. B. Lopukh, I. N. Skrigan, A. V. Vavilov, A. P. Martynov, S. V. Bechta, A. A. Komlev
Publié dans: 2018 International Multi-Conference on Industrial Engineering and Modern Technologies (FarEastCon), 2018, Page(s) 1-6, ISBN 978-1-5386-9535-7
Éditeur: IEEE
DOI: 10.1109/fareastcon.2018.8602779

Evaluation of the Kinetics of Molten Pool Stratification in Case of In-Vessel Melt Retention Strategy

Auteurs: L. Carénini, F. Fichot
Publié dans: Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, 2018, Page(s) V007T11A013, ISBN 978-0-7918-5151-7
Éditeur: ASME
DOI: 10.1115/icone26-82243