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
Main Authors: Charpin, Laurent, Niepceron, Julien, Corbin, Manuel, Masson, Benoît, Mathieu, Jean-Philippe, Haelewyn, Jessica, Hamon, François, Åhs, Magnus, Aparicio, Sofía, Asali, Mehdi, Capra, Bruno, Azenha, Miguel, Bouhjiti, David E.-M., Calonius, Kim, Chu, Meng, Herrman, Nico, Huang, Xu, Jiménez, Sergio, Mazars, Jacky, Mosayan, Mahsa, Nahas, Georges, Stepan, Jan, Thenint, Thibaud, Torrenti, Jean-Michel
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Language:English
Published: Amsterdam Elsevier B.V 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.
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
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  email: julien.niepceron@edf.fr
  organization: EDF DT, Lyon, France
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  email: manuel.corbin@edf.fr
  organization: EDF DT, Lyon, France
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  email: Benoit.masson@edf.fr
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  organization: EDF R&D, EDF Lab Saclay, France
– sequence: 7
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  fullname: Hamon, François
  email: francois.hamon@edf.fr
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  email: magnus.ahs@byggtek.lth.se
  organization: Lund University, Lund, Sweden
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  organization: OXAND, France
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  organization: ISISE, University of Minho, Portugal
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  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
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  givenname: Meng
  surname: Chu
  fullname: Chu, Meng
  email: chumeng@snerdi.com.cn
  organization: Snerdi, China
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  givenname: Nico
  orcidid: 0000-0002-4979-5081
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  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
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  givenname: Sergio
  orcidid: 0000-0001-7982-2725
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  email: sjimenez@cimne.upc.edu
  organization: International Centre for Numerical Methods in Engineering (CIMNE), Barcelona, Spain
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  givenname: Jan
  orcidid: 0000-0001-8691-4118
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  organization: UJV-EGP, Czech Republic
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  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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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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