@inproceedings{b662891665a4446fb0f0d5bd52dd3bf2,
title = "Sensitivity analysis of a nuclear reactor system finite element model",
abstract = "The structures associated with the nuclear steam supply system (NSSS) of a pressurized water reactor (PWR) warrant evaluation of various non-stationary loading conditions which could occur over the life of a nuclear power plant. These loading conditions include those associated with a loss of coolant accident and seismic event. The dynamic structural system is represented by a finite element model consisting of significant epistemic and aleatory uncertainties in the physical parameters. To provide an enhanced understanding of the influence of these uncertainties on model results, a sensitivity analysis is performed. This work demonstrates the construction of a computational design of experiment which runs the finite element model a sufficient number of times to train and verify a unique aggregate surrogate model. Adaptive sampling is employed in order to reduce the overall computational burden. The surrogate model is then used to perform both global and local sensitivity analyses.",
author = "Banyay, {Gregory A.} and Smith, {Stephen D.} and Young, {Jason S.}",
note = "Publisher Copyright: Copyright {\textcopyright} 2018 ASME; ASME 2018 Verification and Validation Symposium, VVS 2018 ; Conference date: 16-05-2018 Through 18-05-2018",
year = "2018",
doi = "10.1115/VVS2018-9306",
language = "English (US)",
series = "ASME 2018 Verification and Validation Symposium, VVS 2018",
publisher = "American Society of Mechanical Engineers (ASME)",
booktitle = "ASME 2018 Verification and Validation Symposium, VVS 2018",
}