Ageing and air leakage assessment of a nuclear reactor containment mock-up: VERCORS 2nd benchmark
•A 1/3 concrete containment building mock-up was built by EDF in France.•An international simulation benchmark has been organised.•The mock-up behaviour (temperature, humidity, strain and leak-tightness evolution) has been predicted by participants. Electricité de France (EDF) operates a large fleet...
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Published in: | Nuclear engineering and design Vol. 377; p. 111136 |
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Main Authors: | , , , , , , , , , , , , , , , , , , , , , , , |
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01-06-2021
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Abstract | •A 1/3 concrete containment building mock-up was built by EDF in France.•An international simulation benchmark has been organised.•The mock-up behaviour (temperature, humidity, strain and leak-tightness evolution) has been predicted by participants.
Electricité de France (EDF) operates a large fleet of nuclear reactors and is responsible for demonstrating the safety of facilities, including concrete containment buildings (CCB), which are non-replaceable components. The leak-tightness of CCBs is assessed every 10 years during integrated leak-rate tests (IRLT). For double-wall containments, which have no metallic liners, the leak-tightness is strongly influenced by the degree of cracking of concrete and opening of the cracks, which mostly depends on (a) the prestress decrease due to the delayed strains of concrete and to a lesser extent due to relaxation of tendons steel, and (b) the saturation degree of the Powered by Editorial Manager® and ProduXion Manager® from Aries Systems Corporation concrete wall. Therefore, to optimize the maintenance programs on CCBs, it is important to predict the evolution of drying, creep and shrinkage strains of concrete to be able to correctly assess the pre-stress losses, and finally the air leak-tightness at a structural level during pressure tests or under accidental loadings.
To improve our understanding and identify the best modelling practices on this issue, a large experimental program called VERCORS was launched in 2014. VERCORS is a 1/3 mock-up of a 1300 MWe nuclear reactor CCB. It has been widely instrumented, and its concrete thoroughly characterized. A specific attention has been paid to ensure it is consistent with real CBBs features in EDF's nuclear fleet. To complement its internal R&D efforts, EDF decided to associate external partners to this program. One of the means for this is the organization of benchmarks, where all teams are given data and information about the mock-up and are asked to quantitatively predict its behaviour. The present paper reports the organization and findings of the 2nd benchmark which was organized in 2018 and gathered several international teams around the same objective: improve the confidence in the modelling of structural behaviour as well as the leak-tightness of concrete in containment walls under pressure test loading.
The benchmark has shown once again that predicting the mechanical and leakage behaviour of containment buildings is a difficult task. The benchmark also yielded interesting information about the possibility to use spatially reduced models to predict the mechanical behaviour and leakage and underlined the fact that more research must be done to better predict the localization of cracks and leakage.
Some lessons have been learnt for the next benchmark: EDF will ask to clarify further the calibration methods, will give more data (including drying, creep and shrinkage at different temperatures and moisture measurements in the mock-up), and will help the participants using local leakage data by projecting the raw measurements on a regular grid, so that the local leakage models can be improved. |
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AbstractList | •A 1/3 concrete containment building mock-up was built by EDF in France.•An international simulation benchmark has been organised.•The mock-up behaviour (temperature, humidity, strain and leak-tightness evolution) has been predicted by participants.
Electricité de France (EDF) operates a large fleet of nuclear reactors and is responsible for demonstrating the safety of facilities, including concrete containment buildings (CCB), which are non-replaceable components. The leak-tightness of CCBs is assessed every 10 years during integrated leak-rate tests (IRLT). For double-wall containments, which have no metallic liners, the leak-tightness is strongly influenced by the degree of cracking of concrete and opening of the cracks, which mostly depends on (a) the prestress decrease due to the delayed strains of concrete and to a lesser extent due to relaxation of tendons steel, and (b) the saturation degree of the Powered by Editorial Manager® and ProduXion Manager® from Aries Systems Corporation concrete wall. Therefore, to optimize the maintenance programs on CCBs, it is important to predict the evolution of drying, creep and shrinkage strains of concrete to be able to correctly assess the pre-stress losses, and finally the air leak-tightness at a structural level during pressure tests or under accidental loadings.
To improve our understanding and identify the best modelling practices on this issue, a large experimental program called VERCORS was launched in 2014. VERCORS is a 1/3 mock-up of a 1300 MWe nuclear reactor CCB. It has been widely instrumented, and its concrete thoroughly characterized. A specific attention has been paid to ensure it is consistent with real CBBs features in EDF's nuclear fleet. To complement its internal R&D efforts, EDF decided to associate external partners to this program. One of the means for this is the organization of benchmarks, where all teams are given data and information about the mock-up and are asked to quantitatively predict its behaviour. The present paper reports the organization and findings of the 2nd benchmark which was organized in 2018 and gathered several international teams around the same objective: improve the confidence in the modelling of structural behaviour as well as the leak-tightness of concrete in containment walls under pressure test loading.
The benchmark has shown once again that predicting the mechanical and leakage behaviour of containment buildings is a difficult task. The benchmark also yielded interesting information about the possibility to use spatially reduced models to predict the mechanical behaviour and leakage and underlined the fact that more research must be done to better predict the localization of cracks and leakage.
Some lessons have been learnt for the next benchmark: EDF will ask to clarify further the calibration methods, will give more data (including drying, creep and shrinkage at different temperatures and moisture measurements in the mock-up), and will help the participants using local leakage data by projecting the raw measurements on a regular grid, so that the local leakage models can be improved. Electricité de France (EDF) operates a large fleet of nuclear reactors and is responsible for demonstrating the safety of facilities, including concrete containment buildings (CCB), which are non-replaceable components. The leak-tightness of CCBs is assessed every 10 years during integrated leak-rate tests (IRLT). For double-wall containments, which have no metallic liners, the leak-tightness is strongly influenced by the degree of cracking of concrete and opening of the cracks, which mostly depends on (a) the prestress decrease due to the delayed strains of concrete and to a lesser extent due to relaxation of tendons steel, and (b) the saturation degree of the Powered by Editorial Manager® and ProduXion Manager® from Aries Systems Corporation concrete wall. Therefore, to optimize the maintenance programs on CCBs, it is important to predict the evolution of drying, creep and shrinkage strains of concrete to be able to correctly assess the pre-stress losses, and finally the air leak-tightness at a structural level during pressure tests or under accidental loadings. To improve our understanding and identify the best modelling practices on this issue, a large experimental program called VERCORS was launched in 2014. VERCORS is a 1/3 mock-up of a 1300 MWe nuclear reactor CCB. It has been widely instrumented, and its concrete thoroughly characterized. A specific attention has been paid to ensure it is consistent with real CBBs features in EDF's nuclear fleet. To complement its internal R&D efforts, EDF decided to associate external partners to this program. One of the means for this is the organization of benchmarks, where all teams are given data and information about the mock-up and are asked to quantitatively predict its behaviour. The present paper reports the organization and findings of the 2nd benchmark which was organized in 2018 and gathered several international teams around the same objective: improve the confidence in the modelling of structural behaviour as well as the leak-tightness of concrete in containment walls under pressure test loading. The benchmark has shown once again that predicting the mechanical and leakage behaviour of containment buildings is a difficult task. The benchmark also yielded interesting information about the possibility to use spatially reduced models to predict the mechanical behaviour and leakage and underlined the fact that more research must be done to better predict the localization of cracks and leakage. Some lessons have been learnt for the next benchmark: EDF will ask to clarify further the calibration methods, will give more data (including drying, creep and shrinkage at different temperatures and moisture measurements in the mock-up), and will help the participants using local leakage data by projecting the raw measurements on a regular grid, so that the local leakage models can be improved. Electricité de France (EDF) operates a large fleet of nuclear reactors and is responsible for demonstrating the safety of facilities, including concrete containment buildings (CCB), which are non-replaceable components. The leak-tightness of CCBs is assessed every 10 years during integrated leak-rate tests (IRLT). For double-wall containments, which have no metallic liners, the leak-tightness is strongly influenced by the degree of cracking of concrete and opening of the cracks, which mostly depends on (a) the prestress decrease due to the delayed strains of concrete, and (b) the saturation degree of the concrete wall. Therefore, to optimize the maintenance programs on CCBs, it is important to predict the evolution of drying, creep shrinkage strains of concrete to be able to correctly assess the pre-stress losses, and finally the air leak-tightness at a structural level during pressure tests or under accidental loadings.To improve our understanding and identify the best modelling practices on this issue, a large experimental program called VERCORS was launched in 2014. VERCORS is a 1/3 mock-up of a 1300 MWe nuclear reactor CCB. It is widely instrumented, and its concrete thoroughly studied. A specific attention has been paid to ensure it is consistent with real CBBs features in EDF’s nuclear fleet.To complement its internal R&D efforts, EDF decided to associate external partners to this program. One of the means for this is the organization of benchmarks, where all teams are given data and information about the mock-up and are asked to forecast its behaviour. The present paper reports the organization and findings of the 2nd benchmark which was organized in 2018 and gathered several international teams around the same objective: improve the confidence in the modelling of structural behaviour as well as the leak-tightness of concrete in containment walls under pressure test loading. |
ArticleNumber | 111136 |
Author | Mosayan, Mahsa Corbin, Manuel Haelewyn, Jessica Calonius, Kim Niepceron, Julien Herrman, Nico Åhs, Magnus Huang, Xu Thenint, Thibaud Capra, Bruno Asali, Mehdi Hamon, François Chu, Meng Mathieu, Jean-Philippe Nahas, Georges Aparicio, Sofía Jiménez, Sergio Charpin, Laurent Masson, Benoît Stepan, Jan Azenha, Miguel Bouhjiti, David E.-M. Torrenti, Jean-Michel Mazars, Jacky |
Author_xml | – sequence: 1 givenname: Laurent surname: Charpin fullname: Charpin, Laurent email: laurent.charpin@edf.fr organization: EDF R&D, EDF Lab Les Renardières, France – sequence: 2 givenname: Julien orcidid: 0000-0003-3438-4797 surname: Niepceron fullname: Niepceron, Julien email: julien.niepceron@edf.fr organization: EDF DT, Lyon, France – sequence: 3 givenname: Manuel surname: Corbin fullname: Corbin, Manuel email: manuel.corbin@edf.fr organization: EDF DT, Lyon, France – sequence: 4 givenname: Benoît surname: Masson fullname: Masson, Benoît email: Benoit.masson@edf.fr organization: EDF DT, Lyon, France – sequence: 5 givenname: Jean-Philippe surname: Mathieu fullname: Mathieu, Jean-Philippe email: jean-hilippe.mathieu@edf.fr organization: EDF R&D, EDF Lab Les Renardières, France – sequence: 6 givenname: Jessica surname: Haelewyn fullname: Haelewyn, Jessica email: haelewyn.jessica@orange.fr organization: EDF R&D, EDF Lab Saclay, France – sequence: 7 givenname: François surname: Hamon fullname: Hamon, François email: francois.hamon@edf.fr organization: EDF R&D, EDF Lab Saclay, France – sequence: 8 givenname: Magnus surname: Åhs fullname: Åhs, Magnus email: magnus.ahs@byggtek.lth.se organization: Lund University, Lund, Sweden – sequence: 9 givenname: Sofía surname: Aparicio fullname: Aparicio, Sofía email: sofia.aparicio@csic.es organization: ITEFI, CSIC, Spain – sequence: 10 givenname: Mehdi orcidid: 0000-0002-6735-5389 surname: Asali fullname: Asali, Mehdi email: mehdi.asali@oxand.com organization: OXAND, France – sequence: 11 givenname: Bruno surname: Capra fullname: Capra, Bruno organization: OXAND, France – sequence: 12 givenname: Miguel surname: Azenha fullname: Azenha, Miguel email: miguel.azenha@civil.uminho.pt organization: ISISE, University of Minho, Portugal – sequence: 13 givenname: David E.-M. surname: Bouhjiti fullname: Bouhjiti, David E.-M. email: david.bouhjiti@egis.fr organization: Univ. Grenoble Alpes, CNRS, Grenoble INP, 3SR, F-38000 Grenoble, France – sequence: 14 givenname: Kim surname: Calonius fullname: Calonius, Kim email: kim.calonius@vtt.fi organization: VTT, Finland – sequence: 15 givenname: Meng surname: Chu fullname: Chu, Meng email: chumeng@snerdi.com.cn organization: Snerdi, China – sequence: 16 givenname: Nico orcidid: 0000-0002-4979-5081 surname: Herrman fullname: Herrman, Nico email: nico.herrmann@mpa-karlsruhe.de organization: Institute of Concrete Structures and Building Materials (IMB), Materials Testing and Research Institute (MPA Karlsruhe), Karlsruhe Institute of Technology (KIT), Germany – sequence: 17 givenname: Xu surname: Huang fullname: Huang, Xu email: xu.huang@mail.utoronto.ca organization: University of Toronto, Canada – sequence: 18 givenname: Sergio orcidid: 0000-0001-7982-2725 surname: Jiménez fullname: Jiménez, Sergio email: sjimenez@cimne.upc.edu organization: International Centre for Numerical Methods in Engineering (CIMNE), Barcelona, Spain – sequence: 19 givenname: Jacky surname: Mazars fullname: Mazars, Jacky email: jacky.mazars@3sr-grenoble.fr organization: Grenoble INP - Engineering Institute, France – sequence: 20 givenname: Mahsa surname: Mosayan fullname: Mosayan, Mahsa email: mahsa.mozayan-kharazi@ingerop.com organization: Ingerop, France – sequence: 21 givenname: Georges surname: Nahas fullname: Nahas, Georges email: georges.nahas@irsn.fr organization: Institute for Radiological and Nuclear Safety (IRSN), B.P. 17 92262 Fontenay-aux-Roses, France – sequence: 22 givenname: Jan orcidid: 0000-0001-8691-4118 surname: Stepan fullname: Stepan, Jan email: jan.stepan1@ujv.cz organization: UJV-EGP, Czech Republic – sequence: 23 givenname: Thibaud surname: Thenint fullname: Thenint, Thibaud email: Thibaut.thenint@necs.fr organization: SIXENSE NECS, France – sequence: 24 givenname: Jean-Michel surname: Torrenti fullname: Torrenti, Jean-Michel email: jean-michel.torrenti@ifsttar.fr organization: Université Gustave Eiffel, France |
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Cites_doi | 10.1007/978-3-319-05194-9 10.2749/nantes.2018.s3-77 10.1016/j.compstruct.2018.05.123 10.1061/(ASCE)0733-9445(2000)126:9(1070) 10.1016/j.nucengdes.2018.04.005 10.1016/j.nucengdes.2013.08.027 10.1016/j.compstruct.2019.02.092 10.1016/j.cemconcomp.2018.04.014 10.1002/nag.2808 10.1016/j.nucengdes.2019.110454 10.3151/jact.14.408 10.1016/S0029-5493(01)00398-3 10.1016/j.engstruct.2018.03.015 10.35789/fib.BULL.0013 10.1016/j.cemconres.2015.11.007 10.21012/FC10.235607 10.1201/9781315182964-27 |
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Keywords | Benchmark Concrete Shrinkage Creep Leak-tightness Containment |
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Snippet | •A 1/3 concrete containment building mock-up was built by EDF in France.•An international simulation benchmark has been organised.•The mock-up behaviour... Electricité de France (EDF) operates a large fleet of nuclear reactors and is responsible for demonstrating the safety of facilities, including concrete... |
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SubjectTerms | Aging Air leakage Benchmark Benchmarks Buildings Calibration Civil Engineering Concrete Concrete construction Containment Containment vessels Cracks Creep Creep (materials) Drying Engineering and Technology Engineering Sciences Génie civil nucléaire Infrastructure Engineering Infrastrukturteknik Leak-tightness Leakage Linings Localization Mechanical properties Mockups Modelling Nuclear engineering Nuclear reactor containment Nuclear reactors Nuclear safety Prestressing Reactors Samhällsbyggnadsteknik Shrinkage Teams Teknik Tendons Tightness |
Title | Ageing and air leakage assessment of a nuclear reactor containment mock-up: VERCORS 2nd benchmark |
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