Benchmarking Standard and Micromechanical Models for Creep and Shrinkage of Concrete Relevant for Nuclear Power Plants

Author:

Šmilauer Vít1ORCID,Dohnalová Lenka1ORCID,Jirásek Milan1ORCID,Sanahuja Julien2ORCID,Seetharam Suresh3ORCID,Babaei Saeid3ORCID

Affiliation:

1. Department of Mechanics, Faculty of Civil Engineering, Czech Technical University in Prague, Thákurova 7, 166 29 Prague, Czech Republic

2. EDF Lab–Département MMC, Site des Renardières–Avenue des Renardières–Ecuelles, 77818 Moret sur Loing, France

3. SCK CEN, Engineered and Geosystems Analysis Unit, Waste and Disposal Expert Group, Boeretang 200, 2400 Mol, Belgium

Abstract

The creep and shrinkage of concrete play important roles for many nuclear power plant (NPP) and engineering structures. This paper benchmarks the standard and micromechanical models using a revamped and appended Northwestern University database of laboratory creep and shrinkage data with 4663 data sets. The benchmarking takes into account relevant concretes and conditions for NPPs using 781 plausible data sets and 1417 problematic data sets, which cover together 47% of the experimental data sets in the database. The B3, B4, and EC2 models were compared using the coefficient of variation of error (CoV) adjusted for the same significance for short-term and long-term measurements. The B4 model shows the lowest variations for autogenous shrinkage and basic and total creep, while the EC2 model performs slightly better for drying and total shrinkage. In addition, confidence levels at 5, 10, 90, and 95% are quantified in every decade. Two micromechanical models, Vi(CA)2T and SCK CEN, use continuum micromechanics for the mean field homogenization and thermodynamics of the water–pore structure interaction. Validations are carried out for the 28-day Young’s modulus of concrete, basic creep compliance, and drying shrinkage of paste and concrete. The Vi(CA)2T model is the second best model for the 28-day Young’s modulus and the basic creep problematic data sets. The SCK CEN micromechanical model provides good prediction for drying shrinkage.

Funder

European Union’s Horizon 2020 EURATOM Work Programme

Publisher

MDPI AG

Subject

General Materials Science

Reference77 articles.

1. Moore, J., Tcherner, J., Naus, D., Bakirov, M., Puttonen, J., and Móga, I. (2016). Ageing Management of Concrete Structures in Nuclear Power Plants, International Atomic Energy Agency.

2. Do, M.J., and Chockie, A.D. (1994). Aging Degradation of Concrete Structures in Nuclear Power Plants, Battelle Seattle Research Center. Report.

3. Basu, P.C., Labbe, P., and Naus, D. (2013, January 18–23). Nuclear power plant concete structures. Proceedings of the 22nd International Conference on Structural Mechanics in Reactor Technology (SMiRT-22), San Francisco, CA, USA.

4. Study on failure mechanism of prestressed concrete containments following a loss of coolant accident;Wang;Eng. Struct.,2020

5. Ageing and air leakage assessment of a nuclear reactor containment mock-up: VERCORS 2nd benchmark;Charpin;Nucl. Eng. Des.,2021

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