Analysis of sensitivity and uncertainty quantification for transient simulation with the emphasis on changes in the transient structure

K. Borowiec, C. Pigg, T. Kozlowski

Research output: Contribution to conferencePaper

Abstract

The sensitivity and uncertainty quantification (UQ) methods were studied in the context of transient simulation results. The influence of simulation parameters on changes in transient structure and occurrence of important phenomena was the focus of the study. Various statistical and data analysis tools were used to investigate the changes in the transient behavior. The NUPEC BWR Full-size Fine-mesh Bundle Test (BFBT) void fraction transients were analyzed. The sensitivity and UQ were studied for the model created using TRAC/RELAP Advanced Computational Engine (TRACE). The pump and turbine trips were simulated using TRACE system code and the code prediction was validated based on void fraction measurement at three axial elevations. The analysis contains a sensitivity study for various simulation parameters. Simulation parameters include boundary conditions, geometry of the facility and physical model parameters. The sensitivity of important simulation parameters was studied using: Pearson’s product momentum correlation coefficient, Sobol’s variance decomposition, Morris screening method, Delta Moment-Independent Analysis, Fourier Amplitude Sensitivity Test (FAST) and Derivative-based Global Sensitivity Measure (DGSM). The methodology of transient sensitivity analysis is presented. The sensitivity and uncertainty study was performed using the TAPE code (Transient Analysis PackagE), a new uncertainty quantification and sensitivity tool developed at the University of Illinois.

Original languageEnglish (US)
Pages5239-5252
Number of pages14
StatePublished - Jan 1 2019
Event18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 - Portland, United States
Duration: Aug 18 2019Aug 23 2019

Conference

Conference18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019
CountryUnited States
CityPortland
Period8/18/198/23/19

Fingerprint

sensitivity
Void fraction
simulation
Engines
Fourier analysis
engines
voids
Transient analysis
Sensitivity analysis
Statistical methods
Momentum
Screening
Turbines
Uncertainty
Boundary conditions
Pumps
Derivatives
Decomposition
sensitivity analysis
turbines

Keywords

  • TAPE
  • Transient sensitivity analysis

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Instrumentation

Cite this

Borowiec, K., Pigg, C., & Kozlowski, T. (2019). Analysis of sensitivity and uncertainty quantification for transient simulation with the emphasis on changes in the transient structure. 5239-5252. Paper presented at 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, Portland, United States.

Analysis of sensitivity and uncertainty quantification for transient simulation with the emphasis on changes in the transient structure. / Borowiec, K.; Pigg, C.; Kozlowski, T.

2019. 5239-5252 Paper presented at 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, Portland, United States.

Research output: Contribution to conferencePaper

Borowiec, K, Pigg, C & Kozlowski, T 2019, 'Analysis of sensitivity and uncertainty quantification for transient simulation with the emphasis on changes in the transient structure' Paper presented at 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, Portland, United States, 8/18/19 - 8/23/19, pp. 5239-5252.
Borowiec K, Pigg C, Kozlowski T. Analysis of sensitivity and uncertainty quantification for transient simulation with the emphasis on changes in the transient structure. 2019. Paper presented at 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, Portland, United States.
Borowiec, K. ; Pigg, C. ; Kozlowski, T. / Analysis of sensitivity and uncertainty quantification for transient simulation with the emphasis on changes in the transient structure. Paper presented at 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, Portland, United States.14 p.
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