Comparative study of the prediction of delayed strains using the next-generation Eurocode2 with measurements on structures

References

• Abrishami, H., Tcherner, J., Barre, F., Borgerhoff, M., Bumann, U., Calonius, K., Courtois, A., Debattista, J., Gallitre, E., Isard, C., Elison, O., Graves, H., Sircar, M., Huerta, A., White, A., Jackson, P., Kjellin, D., Lillhoek, S., Louhivirta, J., … Varpasuo, P. (2015). Bonded or unbonded technologies for nuclear reactor prestressed concrete containments (No. NEA-CSNI-R–2015-5). Organisation for Economic Co-Operation and Development.
   Google Scholar
• AFNOR. (2005). NF EN 1992-2 – Eurocode 2 – Design of concrete structures – Part 2: Concrete bridges—Design and detailing rules (2005).
   Google Scholar
• AFNOR. (2007). NF EN1992-1-1 NA – Eurocode 2: Calcul des structures en béton—Partie 1-1: Règles générales et règles pour les bâtiments - Annexe Nationale à la NF EN 1992-1-1: (2005).
   Google Scholar
• Aili, A., & Torrenti, J. M. (2020). Modeling long-term delayed strains of prestressed concrete with real temperature and relative humidity history. Journal of Advanced Concrete Technology, 18(7), 396–408. https://doi.org/10.3151/jact.18.396
   Web of Science ®Google Scholar
• Aili, A., Torrenti, J. M., Sellin, J. P., Barthelemy, J. F., & Vandamme, M. (2023). On the long-term delayed strain of concrete structures. Cement and Concrete Research, 165, 107086. https://doi.org/10.1016/j.cemconres.2022.107086
   Web of Science ®Google Scholar
• Aili, A., Torrenti, J. M., Barre, F., & Caba, L. (2024). Delayed deformation of confinement buildings: 30-Year in situ measured data and prediction with the next-generation Eurocode-2. Structural Concrete, 25(3), 1702–1712. https://doi.org/10.1002/suco.202300665
   Web of Science ®Google Scholar
• Anderson, P. (2005). Thirty years of measured prestress at Swedish nuclear reactor containments. Nuclear Engineering and Design, 235(21), 2323–2336. https://doi.org/10.1016/j.nucengdes.2005.04.002
   Web of Science ®Google Scholar
• Bažant, Z. P., Hubler, M. H., & Yu, Q. (2011). Excessive creep deflections: An awakening. Concrete International, 33(8), 44–46.
   Google Scholar
• Bažant, Z. P., Yu, Q., & Li, G. H. (2012). Excessive long-time deflections of prestressed box girders. I: Record-span bridge in Palau and other paradigms. Journal of Structural Engineering, 138(6), 676–686. https://doi.org/10.1061/(ASCE)ST.1943-541X.0000487
   Web of Science ®Google Scholar
• Bažant, Z. P., Yu, Q., & Li, G. H. (2012). Excessive long-time deflections of prestressed box girders. II: Numerical analysis and lessons learned. Journal of Structural Engineering, 138(6), 687–696. https://doi.org/10.1061/(ASCE)ST.1943-541X.0000375
   Web of Science ®Google Scholar
• Bouhjiti, D. M., Boucher, M., Briffaut, M., Dufour, F., Baroth, J., & Masson, B. (2018). Accounting for realistic thermo-hydro-mechanical boundary conditions whilst modeling the ageing of concrete in nuclear containment buildings: Model validation and sensitivity analysis. Engineering Structures, 166, 314–338. https://doi.org/10.1016/j.engstruct.2018.03.015
   Web of Science ®Google Scholar
• CEN. (2022). FprEN 1992-1-1:2022, Eurocode 2: Design of concrete structures - Part 1-1: General rules - Rules for buildings, bridges and civil engineering structures.
   Google Scholar
• Charpin, L., Niepceron, J., Corbin, M., Masson, B., Mathieu, J.-P., Haelewyn, J., Hamon, F., Åhs, M., Aparicio, S., Asali, M., Capra, B., AzeNHa, M., Bouhjiti, D. E.-M., Calonius, K., Chu, M., Herrman, N., Huang, X., Jiménez, S., Mazars, J., … Torrenti, J.-M. (2021). Ageing and air leakage assessment of a nuclear reactor containment mock-up: VERCORS 2nd benchmark. Nuclear Engineering and Design, 377, 111136. https://doi.org/10.1016/j.nucengdes.2021.111136
   Web of Science ®Google Scholar
• Costaz, J. L., Picaut, J., & Barre, F. (1983). Evolution of the concrete containment in the French PWR program – SMIRT 7th. http://www.lib.ncsu.edu/resolver/1840.20/26056
   Google Scholar
• Costaz, J. L., Rousselle, H., Picaut, J., & Chataigner, J. (1989). Delayed analysis from French PWR 900 MW containment monitoring comparison with foreseen design values SMIRT 10.
   Google Scholar
• fib. (2012). fib Bulletin 65: Model Code 2010 Vol. 1.
   Google Scholar
• Granger, L. (1995). Comportement différé du béton dans les enceintes de centrales nucléaires: analyse et modélisation [Ph.D. thesis]. Ecole Nationale des Ponts et Chaussées.
   Google Scholar
• Hora, Z., & Patzák, B. (2007). Analysis of long-term behaviour of nuclear reactor containment. Nuclear Engineering and Design, 237(3), 253–259. https://doi.org/10.1016/j.nucengdes.2006.06.009
   Web of Science ®Google Scholar
• Lundqvist, P., & Nilsson, L. O. (2011). Evaluation of prestress losses in nuclear reactor containments. Nuclear Engineering and Design, 241(1), 168–176. https://doi.org/10.1016/j.nucengdes.2010.11.007
   Web of Science ®Google Scholar
• Müller, H. S., Anders, I., Breiner, R., & Vogel, M. (2013). Concrete: Treatment of types and properties in fib Model Code 2010. Structural Concrete, 14(4), 320–334. https://doi.org/10.1002/suco.201200048
   Web of Science ®Google Scholar
• Shurbert-Hetzel, C., Daneshvar, D., Robisson, A., & Shafei, B. (2023). Data-enabled comparison of six prediction models for concrete shrinkage and creep. Case Studies in Construction Materials, 19, e02406. https://doi.org/10.1016/j.cscm.2023.e02406
   Google Scholar
• Simon, A., & Courtois, A. (2011). Structural monitoring of prestressed concrete containments of nuclear power plants for ageing management. Structural Mechanics in Reactor Technology, 21, 6–11.
   Google Scholar
• Šmilauer, V., Dohnalová, L., Jirásek, M., Sanahuja, J., Seetharam, S., & Babaei, S. (2023). Benchmarking standard and micromechanical models for creep and shrinkage of concrete relevant for nuclear power plants. Materials, 16(20), 6751. https://doi.org/10.3390/ma16206751
   PubMed Web of Science ®Google Scholar
• Song, H. W., Kim, S. H., Byun, K. J., & Song, Y. C. (2002). Creep prediction of concrete for reactor containment structures. Nuclear Engineering and Design, 217(3), 225–236. https://doi.org/10.1016/S0029-5493(02)00135-8
   Web of Science ®Google Scholar
• Wendner, R., Hubler, M. H., & Bažant, Z. P. (2015). Optimization method, choice of form and uncertainty quantification of Model B4 using laboratory and multi-decade bridge databases. Materials and Structures, 48(4), 771–796. https://doi.org/10.1617/s11527-014-0515-0
   Web of Science ®Google Scholar