The Advanced Gas-Cooled Reactors (AGR) are the backbone of the UK's nuclear generation fleet, producing ~17% of the country's electricity. Their safety cases are supported by thorough inspection and monitoring of their graphite cores and extensive theoretical, analytical and experimental studies. This paper presents a unique, highly innovative and technically challenging earthquake engineering project that has provided vital evidence to underpin the seismic safety assessments of the AGRs. Two modelling approaches, one experimental (a multi-layer array physical model) and one numerical (a SOLFEC non-smooth contact dynamics computational model) have been developed to investigate the seismic behaviour of an aged graphite core. The synergetic relationship between the two approaches is a product of insightful collaborative learning between the University of Bristol and Atkins, with the experiments providing material parameters and validation data and the computer simulations feeding array design and test schedule recommendations to the physical model. The predictive capabilities of the physical and the numerical models are tested by direct comparison and the good agreement between the results has increased the confidence in both. The model’s versatility allows a variety of core scenarios to be tested that can explore in detail the AGR core behaviour in seismic conditions.
Dihoru, L., Cannell, B., Oddbjornsson, O., Crewe , A. J., Horseman, T., Dietz, M., & Taylor, C. A. (2020). EXPERIMENTAL AND COMPUTATIONAL SYNERGY FOR MODELLING AN ADVANCED GAS-COOLED REACTOR CORE UNDER SEISMIC EXCITATION. Earthquake Engineering and Structural Dynamics, 1-20. [https://onlinelibrary.wiley.com/doi/full/10.1002/eqe.3291]. https://doi.org/10.1002/eqe.3291