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

Información del proyecto

IVMR

Identificador del acuerdo de subvención: 662157

DOI

10.3030/662157

Proyecto cerrado

Fecha de la firma de la CE 20 Mayo 2015

Fecha de inicio 1 Junio 2015

Fecha de finalización 30 Noviembre 2019

Financiado con arreglo a

• Euratom

Coste total

€ 8 262 989,38

Aportación de la UE

€ 4 831 454,00

Coordinado por

INSTITUT DE RADIOPROTECTION ET DE SURETE NUCLEAIRE
France

CORDIS proporciona enlaces a los documentos públicos y las publicaciones de los proyectos de los programas marco HORIZONTE.

Los enlaces a los documentos y las publicaciones de los proyectos del Séptimo Programa Marco, así como los enlaces a algunos tipos de resultados específicos, como conjuntos de datos y «software», se obtienen dinámicamente de OpenAIRE .

Resultado final

Documents, reports (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

Demonstrators, pilots, prototypes (1)

IVMR website

Creation of IVMR website

Publicaciones

Peer reviewed articles (15)

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

Autores: F. Fichot, L. Carénini, M. Sangiorgi, S. Hermsmeyer, A. Miassoedov, S. Bechta, J. Zdarek, D. Guenadou
Publicado en: Annals of Nuclear Energy, Edición 119, 2018, Página(s) 36-45, ISSN 0306-4549
Editor: 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

Autores: R. Gencheva, A. Stefanova, P. Groudev
Publicado en: Annals of Nuclear Energy, Edición 81, 2015, Página(s) 207-212, ISSN 0306-4549
Editor: 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

Autores: L. Carénini, F. Fichot, N. Seignour
Publicado en: Annals of Nuclear Energy, Edición 118, 2018, Página(s) 363-374, ISSN 0306-4549
Editor: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2018.04.032

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

Autores: R. Gencheva, A. Stefanova, P. Groudev, B. Chatterjee, D. Mukhopadhyay
Publicado en: Nuclear Engineering and Design, Edición 298, 2016, Página(s) 208-217, ISSN 0029-5493
Editor: 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

Autores: Didier Jacquemain, Didier Vola, Renaud Meignen, Jean-Michel Bonnet, Florian Fichot, Emmanuel Raimond, Marc Barrachin
Publicado en: Nuclear Technology, Edición 196/2, 2016, Página(s) 161-174, ISSN 0029-5450
Editor: American Nuclear Society
DOI: 10.13182/NT16-13

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

Autores: Peter Matejovic, Miroslav Barnak, Milan Bachraty, Lubomir Vranka, Robert Berky
Publicado en: Nuclear Engineering and Design, Edición 314, 2017, Página(s) 93-109, ISSN 0029-5493
Editor: Elsevier BV
DOI: 10.1016/j.nucengdes.2017.01.015

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

Autores: Afaque Shams
Publicado en: Annals of Nuclear Energy, Edición 117, 2018, Página(s) 234-246, ISSN 0306-4549
Editor: 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

Autores: Mindaugas Valinčius, Tadas Kaliatka, Algirdas Kaliatka, Eugenijus Ušpuras
Publicado en: Science and Technology of Nuclear Installations, Edición 2018, 2018, Página(s) 1-14, ISSN 1687-6075
Editor: Hindawi Publishing Corporation
DOI: 10.1155/2018/7162387

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

Autores: Alice Seibert, Dragos Staicu, David Bottomley, Marco Cologna, Jacobus Boshoven, Herwin Hein, Emthetal Kassim, Sarah Nourry, Markus Ernstberger, Davide Robba, Rudy Konings
Publicado en: Journal of Nuclear Materials, Edición 520, 2019, Página(s) 165-177, ISSN 0022-3115
Editor: 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

Autores: Adrien Pivano, Pascal Piluso, Nourdine Chikhi, Jules Delacroix, Pascal Fouquart, Romain Le Tellier
Publicado en: Nuclear Engineering and Design, Edición 355, 2019, Página(s) 110271, ISSN 0029-5493
Editor: 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

Autores: N. Chikhi, P. Fouquart, J. Delacroix, P. Piluso
Publicado en: Nuclear Technology, Edición 205/1-2, 2018, Página(s) 200-212, ISSN 0029-5450
Editor: American Nuclear Society
DOI: 10.1080/00295450.2018.1486160

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

Autores: L. Carénini, F. Fichot, N. Bakouta, A. Filippov, R. Le Tellier, L. Viot, I. Melnikov, P. Pandazis
Publicado en: Annals of Nuclear Energy, Edición 146, 2020, Página(s) 107612, ISSN 0306-4549
Editor: 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

Autores: Xiaoyang Gaus-Liu, Thomas Cron, Beatrix Fluhrer
Publicado en: Nuclear Technology, 2020, Página(s) 1-12, ISSN 0029-5450
Editor: American Nuclear Society
DOI: 10.1080/00295450.2020.1743102

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

Autores: 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
Publicado en: Annals of Nuclear Energy, Edición 146, 2020, Página(s) 107617, ISSN 0306-4549
Editor: 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

Autores: Shambhavi Nandan, Florian Fichot, Bruno Piar
Publicado en: Nuclear Engineering and Design, Edición 364, 2020, Página(s) 110608, ISSN 0029-5493
Editor: Elsevier BV
DOI: 10.1016/j.nucengdes.2020.110608

Conference proceedings (4)

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

Autores: L. Carénini, F. Fichot
Publicado en: 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, Página(s) V004T13A009, ISBN 978-0-7918-5004-6
Editor: ASME
DOI: 10.1115/ICONE24-60598

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

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

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

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

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

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