TY - JOUR
T1 - Machine learning approaches for performance assessment of nuclear fuel assemblies subject to seismic-induced impacts
AU - Altieri, Domenico
AU - Robin-Boudaoud, Marie Cécile
AU - Kessler, Hannes
AU - Pellissetti, Manuel
AU - Patelli, Edoardo
N1 - Funding Information: EPSRC and ESRC Center for Doctoral Training on Quantifi-cation and Management of Risk and Uncertainty in Complex Systems and Environments (Grant No. EP/L015927/1; Funder ID: 10.13039/501100000266).
Funding Information: EPSRC project A Resilience Modelling Framework for Improved Nuclear Safety (NuRes) (Grant No. EP/R020558/2; Funder ID: 10.13039/501100000266).
Funding Information: The authors would like to acknowledge the gracious support of this work through the EPSRC and ESRC Center for Doctoral Training on Quantification and Management of Risk and Uncertainty in Complex Systems and Environments Grant number (EP/L015927/1).
Publisher Copyright: © 2020 by ASME.
PY - 2020/6/8
Y1 - 2020/6/8
N2 - In pressurized water nuclear reactors, the seismic performance of fuel assemblies is governed by their spacer grids (SGs) which may experience impacts with neighboring fuel assembly SGs or with the core barrel, depending on the intensity of the seismic event. Nonlinear dynamic analysis aiming at computing the maximum permanent deformation in a statistic framework is computationally demanding due to the different possible core configurations and the dimension of the dataset of seismic excitations. Hence, surrogate models trained by the physics-based dynamic model are proposed to analyze different scenarios, i.e., explore the space of potential core configurations and seismic excitations. Starting from ground motion records corresponding to six levels of seismic hazard, the dynamic excitation at the elevation of the reactor pressure vessel is obtained via transfer functions. Correlation between different seismic intensity measures and the maximum permanent deformation is evaluated. The performance of two well-established surrogate models, namely, artificial neural networks (ANN) and Gaussian process (GP) for regression problems is analyzed and discussed. Bayesian techniques are adopted to enhance the robustness of the trained surrogate models by training sets of neural networks and estimating the hyper-parameter of the GP.
AB - In pressurized water nuclear reactors, the seismic performance of fuel assemblies is governed by their spacer grids (SGs) which may experience impacts with neighboring fuel assembly SGs or with the core barrel, depending on the intensity of the seismic event. Nonlinear dynamic analysis aiming at computing the maximum permanent deformation in a statistic framework is computationally demanding due to the different possible core configurations and the dimension of the dataset of seismic excitations. Hence, surrogate models trained by the physics-based dynamic model are proposed to analyze different scenarios, i.e., explore the space of potential core configurations and seismic excitations. Starting from ground motion records corresponding to six levels of seismic hazard, the dynamic excitation at the elevation of the reactor pressure vessel is obtained via transfer functions. Correlation between different seismic intensity measures and the maximum permanent deformation is evaluated. The performance of two well-established surrogate models, namely, artificial neural networks (ANN) and Gaussian process (GP) for regression problems is analyzed and discussed. Bayesian techniques are adopted to enhance the robustness of the trained surrogate models by training sets of neural networks and estimating the hyper-parameter of the GP.
KW - machine Learning
KW - nuclear fuel assemblies
KW - seismic-induced impacts
KW - pressurized water nuclear reactors
KW - spacer grids (SGs)
KW - nonlinear dynamic analysis
KW - physics-based dynamic model
KW - artificial neural networks
UR - http://www.scopus.com/inward/record.url?scp=85102436607&partnerID=8YFLogxK
U2 - 10.1115/1.4046926
DO - 10.1115/1.4046926
M3 - Article
AN - SCOPUS:85102436607
SN - 2332-9017
VL - 6
JO - ASCE-ASME Journal of Risk and Uncertainty in Engineering Systems, Part B: Mechanical Engineering
JF - ASCE-ASME Journal of Risk and Uncertainty in Engineering Systems, Part B: Mechanical Engineering
IS - 4
M1 - 041002
ER -