Explore the words cloud of the IVMR project. It provides you a very rough idea of what is the project "IVMR" about.
The following table provides information about the project.
Coordinator |
INSTITUT DE RADIOPROTECTION ET DE SURETE NUCLEAIRE
Organization address contact info |
Coordinator Country | France [FR] |
Project website | https://gforge.irsn.fr/gf/project/ivmr/ |
Total cost | 8˙262˙989 € |
EC max contribution | 4˙831˙454 € (58%) |
Programme |
1. H2020-Euratom-1.8. (Ensure availability and use of research infrastructures of pan_european relevance) 2. H2020-Euratom-1.3. (Support the development and sustainability of nuclear competences at Union level) 3. H2020-Euratom-1.1. (Support safe operation of nuclear systems) |
Code Call | NFRP-2014-2015 |
Funding Scheme | RIA |
Starting year | 2015 |
Duration (year-month-day) | from 2015-06-01 to 2019-11-30 |
Take a look of project's partnership.
The stabilization of molten corium is recognised as essential if a safe and stable state is to be reached following a severe accident. Among the possible options, In-Vessel Melt Retention (IVMR) appears as an attractive solution that would minimize the risks of containment failure (less Hydrogen produced, no corium-concrete interaction), if it can be proved to be feasible. The strategy is already adopted for the VVER 440 type 213 based on thorough research work for the Finnish Loviisa NPP and Hungarian Paks NPP. It is also included in the design of some new Gen.III reactors like AP-1000, APR 1400 and Chinese CPR-1000. It has also been studied in the past for other reactor concepts like KERENA (BWR) or VVER-640. Current approaches for reactors with relatively small power, such as VVER 440 or AP600, use conservative assumptions. However, for higher power reactors (around 1000 MWe), it is necessary to evaluate the IVMR strategy with best-estimate methods in order to address the uncertainties associated with the involved phenomena. Additional R&D is needed to ensure and demonstrate adequate safety margins, including identification of efficient technical solutions for the external cooling of the vessel and performing best-estimate evaluation of relevant scenarios. Among other provisions, the possibility of cooling the corium inside the vessel by direct injection of water into the degraded core, may be considered because it is likely to remove a significant part of the residual power. The goal of the project is an analysis of the applicability and technical feasibility of the IVMR strategy to high power reactors, both for existing ones (e.g. VVER 1000 type 320 units) as well as for future reactors of different types (PWR or BWR). The main outcomes of the project will be elevant assumptions and scenarios to estimate the maximum heat load on the vessel wall, improved numerical tools for the analysis of IVMR issues and a harmonized methodology on the IVMR.
Final report on simulant stratified pool | Documents, reports | 2020-03-13 11:49:07 |
Final report on top cooling | Documents, reports | 2020-03-13 10:23:29 |
Final project report | Documents, reports | 2020-03-13 11:18:37 |
Report on CERES tests | Documents, reports | 2020-03-13 11:17:05 |
Synthesis report on spray cooling | Documents, reports | 2020-03-11 10:38:05 |
Report on experimental study of spray cooling | Documents, reports | 2020-03-06 14:57:10 |
Review of alternative innovations | Documents, reports | 2020-03-06 14:57:03 |
Synthesis report on corium pool behaviour | Documents, reports | 2020-03-06 14:56:38 |
Final report on the large scale cold-crucible experiment | Documents, reports | 2020-03-06 14:56:48 |
Review of spray cooling | Documents, reports | 2020-03-06 14:56:49 |
Report on mechanical resistance | Documents, reports | 2020-03-06 14:56:42 |
Review of vessel coating | Documents, reports | 2020-03-06 14:56:53 |
Report on the use of CFD | Documents, reports | 2020-03-06 14:57:11 |
Communication action Plan | Documents, reports | 2020-03-06 14:57:01 |
Final report on critical scenarios | Documents, reports | 2020-02-27 15:44:32 |
Methodology - Synthesis | Documents, reports | 2020-02-14 10:25:41 |
Final report on core debris coolability | Documents, reports | 2020-02-14 10:25:41 |
Results of the PIRT on phenomena relevant for IVR modelling | Documents, reports | 2020-02-14 10:25:41 |
Final report on innovations | Documents, reports | 2020-02-14 10:25:41 |
Review of baffling of the vessel | Documents, reports | 2020-02-14 10:25:41 |
Final report on full scale tests | Documents, reports | 2020-02-14 10:25:40 |
Report on modelling | Documents, reports | 2020-02-14 10:25:41 |
Final report on oxide conductivity | Documents, reports | 2020-02-14 10:25:40 |
Review of active passive/injection systems | Documents, reports | 2020-02-14 10:25:40 |
Final report on melt properties | Documents, reports | 2020-02-14 10:25:40 |
Influence of oxidation and fluid properties on boiling and CHF: Results of the CNU-M1 and ANUBIS tests | Documents, reports | 2020-02-14 10:25:40 |
3rd periodic report | Documents, reports | 2020-02-14 10:25:40 |
Final report on core reflood | Documents, reports | 2020-02-14 10:25:40 |
Review of instrumentation for SAMG | Documents, reports | 2020-02-14 10:25:40 |
First periodic report | Documents, reports | 2020-02-14 10:25:39 |
IVMR website | Demonstrators, pilots, prototypes | 2020-02-14 10:25:39 |
2nd periodic report | Documents, reports | 2020-02-14 10:25:39 |
Preliminary report on spray cooling | Documents, reports | 2020-02-14 10:25:39 |
Minutes of the kick-off meeting | Documents, reports | 2020-02-14 10:25:39 |
Final report on small scale tests | Documents, reports | 2020-02-14 10:25:39 |
Take a look to the deliverables list in detail: detailed list of IVMR deliverables.
year | authors and title | journal | last update |
---|---|---|---|
2019 |
Adrien Pivano, Pascal Piluso, Nourdine Chikhi, Jules Delacroix, Pascal Fouquart, Romain Le Tellier Experiments on interactions of molten steel with suboxidized corium crust for in-vessel melt retention published pages: 110271, ISSN: 0029-5493, DOI: 10.1016/j.nucengdes.2019.110271 |
Nuclear Engineering and Design 355 | 2020-02-14 |
2018 |
N. Chikhi, P. Fouquart, J. Delacroix, P. Piluso Measurement of Type 304L Stainless Steel and 16MND5 Ferritic Steel Density and Surface Tension: Possible Impact for Stratified Molten Pool published pages: 200-212, ISSN: 0029-5450, DOI: 10.1080/00295450.2018.1486160 |
Nuclear Technology 205/1-2 | 2020-02-14 |
2019 |
Alice Seibert, Dragos Staicu, David Bottomley, Marco Cologna, Jacobus Boshoven, Herwin Hein, Emthetal Kassim, Sarah Nourry, Markus Ernstberger, Davide Robba, Rudy Konings Thermophysical properties of U, Zr-oxides as prototypic corium materials published pages: 165-177, ISSN: 0022-3115, DOI: 10.1016/j.jnucmat.2019.04.019 |
Journal of Nuclear Materials 520 | 2020-02-14 |
2018 |
F. Fichot, L. Carénini, M. Sangiorgi, S. Hermsmeyer, A. Miassoedov, S. Bechta, J. Zdarek, D. Guenadou Some considerations to improve the methodology to assess In-Vessel Retention strategy for high-power reactors published pages: 36-45, ISSN: 0306-4549, DOI: 10.1016/j.anucene.2018.03.040 |
Annals of Nuclear Energy 119 | 2020-02-14 |
2018 |
Mindaugas ValinÄius, Tadas Kaliatka, Algirdas Kaliatka, Eugenijus UÅ¡puras Modelling of Severe Accident and In-Vessel Melt Retention Possibilities in BWR Type Reactor published pages: 1-14, ISSN: 1687-6075, DOI: 10.1155/2018/7162387 |
Science and Technology of Nuclear Installations 2018 | 2020-02-14 |
2015 |
R. Gencheva, A. Stefanova, P. Groudev Plant application of ICARE/ASTECv2.0r3 computer code for investigation of in-vessel melt retention in VVER-1000 reactor design published pages: 207-212, ISSN: 0306-4549, DOI: 10.1016/j.anucene.2015.02.039 |
Annals of Nuclear Energy 81 | 2020-02-14 |
2018 |
L. Carénini, F. Fichot, N. Seignour Modelling issues related to molten pool behaviour in case of In-Vessel Retention strategy published pages: 363-374, ISSN: 0306-4549, DOI: 10.1016/j.anucene.2018.04.032 |
Annals of Nuclear Energy 118 | 2020-02-14 |
2018 |
Afaque Shams Towards the accurate numerical prediction of thermal hydraulic phenomena in corium pools published pages: 234-246, ISSN: 0306-4549, DOI: 10.1016/j.anucene.2018.03.031 |
Annals of Nuclear Energy 117 | 2020-02-14 |
2017 |
Peter Matejovic, Miroslav Barnak, Milan Bachraty, Lubomir Vranka, Robert Berky Adoption of in-vessel retention concept for VVER-440/V213 reactors in Central European Countries published pages: 93-109, ISSN: 0029-5493, DOI: 10.1016/j.nucengdes.2017.01.015 |
Nuclear Engineering and Design 314 | 2020-02-14 |
2016 |
R. Gencheva, A. Stefanova, P. Groudev, B. Chatterjee, D. Mukhopadhyay Study of in-vessel melt retention for VVER-1000/v320 reactor published pages: 208-217, ISSN: 0029-5493, DOI: 10.1016/j.nucengdes.2015.12.031 |
Nuclear Engineering and Design 298 | 2020-02-14 |
2016 |
Didier Jacquemain, Didier Vola, Renaud Meignen, Jean-Michel Bonnet, Florian Fichot, Emmanuel Raimond, Marc Barrachin Past and Future Research at IRSN on Corium Progression and Related Mitigation Strategies in a Severe Accident published pages: 161-174, ISSN: 0029-5450, DOI: 10.13182/NT16-13 |
Nuclear Technology 196/2 | 2020-02-14 |
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