Sensitivity analysis of an Advanced Gas-cooled Reactor control rod model

Scott, M, Green, PL, O’Driscoll, D, Worden, K and Sims, N
(2016) Sensitivity analysis of an Advanced Gas-cooled Reactor control rod model. Nuclear Engineering and Design, 305. pp. 514-523.

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A model has been made of the primary shutdown system of an Advanced Gas-cooled Reactor nuclear power station. The aim of this paper is to explore the use of sensitivity analysis techniques on this model. The two motivations for performing sensitivity analysis are to quantify how much individual uncertain parameters are responsible for the model output uncertainty, and to make predictions about what could happen if one or several parameters were to change. Global sensitivity analysis techniques were used based on Gaussian process emulation; the software package GEM-SA was used to calculate the main effects, the main effect index and the total sensitivity index for each parameter and these were compared to local sensitivity analysis results. The results suggest that the system performance is resistant to adverse changes in several parameters at once.

Item Type: Article
Additional Information: Date: 2015-04-07 (submitted)
Depositing User: Symplectic Admin
Date Deposited: 26 Mar 2019 11:35
Last Modified: 15 Mar 2024 14:54
DOI: 10.1016/j.nucengdes.2016.06.005
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