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IVMR SIGNED

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

Total Cost €

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EC-Contrib. €

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Partnership

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Project "IVMR" data sheet

The following table provides information about the project.

Coordinator
INSTITUT DE RADIOPROTECTION ET DE SURETE NUCLEAIRE 

Organization address
address: AV DE LA DIVISION LECLERC 31
city: FONTENAY AUX ROSES
postcode: 92260
website: http://www.irsn.org

contact info
title: n.a.
name: n.a.
surname: n.a.
function: n.a.
email: n.a.
telephone: n.a.
fax: n.a.

 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

 Partnership

Take a look of project's partnership.

# participants  country  role  EC contrib. [€] 
1    INSTITUT DE RADIOPROTECTION ET DE SURETE NUCLEAIRE FR (FONTENAY AUX ROSES) coordinator 840˙130.00
2    KUNGLIGA TEKNISKA HOEGSKOLAN SE (STOCKHOLM) participant 1˙078˙701.00
3    UJV REZ, a. s. CZ (HUSINEC) participant 663˙397.00
4    COMMISSARIAT A L ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES FR (PARIS 15) participant 550˙682.00
5    KARLSRUHER INSTITUT FUER TECHNOLOGIE DE (KARLSRUHE) participant 319˙937.00
6    JRC -JOINT RESEARCH CENTRE- EUROPEAN COMMISSION BE (BRUSSELS) participant 293˙215.00
7    ELECTRICITE DE FRANCE FR (PARIS 08) participant 125˙044.00
8    AGENZIA NAZIONALE PER LE NUOVE TECNOLOGIE, L'ENERGIA E LO SVILUPPO ECONOMICO SOSTENIBILE IT (ROMA) participant 109˙125.00
9    INZINIERSKA VYPOCTOVA SPOLOCNOST TRNAVA S.R.O. SK (TRNAVA) participant 108˙500.00
10    HELMHOLTZ-ZENTRUM DRESDEN-ROSSENDORF EV DE (DRESDEN) participant 96˙600.00
11    AREVA NP SAS FR (COURBEVOIE) participant 82˙875.00
12    Teknologian tutkimuskeskus VTT Oy FI (Espoo) participant 80˙456.00
13    CENTRUM VYZKUMU REZ SRO CZ (HUSINEC-REZ) participant 80˙000.00
14    NUCLEAR RESEARCH AND CONSULTANCY GROUP NL (PETTEN) participant 69˙825.00
15    IMPERIAL COLLEGE OF SCIENCE TECHNOLOGY AND MEDICINE UK (LONDON) participant 58˙030.00
16    NARODOWE CENTRUM BADAN JADROWYCH PL (OTWOCK) participant 57˙600.00
17    Fortum Power and Heat Oy FI (Espoo) participant 47˙812.00
18    ENERGIATUDOMANYI KUTATOKOZPONT HU (Budapest) participant 46˙000.00
19    NUBIKI Nuclear Safety Research Institute Ltd. HU (BUDAPEST) participant 45˙375.00
20    INSTITUTE OF NUCLEAR RESEARCH AND NUCLEAR ENERGY - BULGARIAN ACADEMY OF SCIENCES BG (SOFIA) participant 41˙400.00
21    LIETUVOS ENERGETIKOS INSTITUTAS LT (KAUNAS) participant 28˙875.00
22    TRACTEBEL ENGINEERING BE (BRUXELLES) participant 7˙875.00
23    GESELLSCHAFT FUR ANLAGEN UND REAKTORSICHERHEIT (GRS) gGmbH DE (KOLN) participant 0.00

Map

 Project objective

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.

 Deliverables

List of deliverables.
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.

 Publications

year authors and title journal last update
List of publications.
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 Valinčius, Tadas Kaliatka, Algirdas Kaliatka, Eugenijus Ušpuras
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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