Inverse uncertainty quantification of reactor simulations under the Bayesian framework using surrogate models constructed by polynomial chaos expansion
Creators
Description
Modeling and simulations are naturally augmented by extensive Uncertainty Quantification (UQ) and sensitivity analysis requirements in the nuclear reactor system design, in which uncertainties must be quantified in order to prove that the investigated design stays within acceptance criteria. Historically, expert judgment has been used to specify the nominal values, probability density functions and upper and lower bounds of the simulation code random input parameters for the forward UQ process. The purpose of this paper is to replace such ad-hoc expert judgment of the statistical properties of input model parameters with inverse UQ process. Inverse UQ seeks statistical descriptions of the model random input parameters that are consistent with the experimental data. Bayesian analysis is used to establish the inverse UQ problems based on experimental data, with systematic and rigorously derived surrogate models based on Polynomial Chaos Expansion (PCE). The methods developed here are demonstrated with the Point Reactor Kinetics Equation (PRKE) coupled with lumped parameter thermal-hydraulics feedback model. Three input parameters, external reactivity, Doppler reactivity coefficient and coolant temperature coefficient are modeled as uncertain input parameters. Their uncertainties are inversely quantified based on synthetic experimental data. Compared with the direct numerical simulation, surrogate model by PC expansion shows high efficiency and accuracy. In addition, inverse UQ with Bayesian analysis can calibrate the random input parameters such that the simulation results are in a better agreement with the experimental data.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2016.11.032Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2016.11.032;
- PII
- S0029-5493(16)30482-4;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 313
- Journal Page Range
- p. 29-52
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48062554
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- CHAOS THEORY; COMPUTERIZED SIMULATION; COOLANTS; DOPPLER COEFFICIENT; EXPERIMENTAL DATA; POLYNOMIALS; PROBABILITY DENSITY FUNCTIONS; REACTOR DESIGN; REACTOR KINETICS EQUATIONS; SENSITIVITY ANALYSIS; TEMPERATURE COEFFICIENT; THERMAL HYDRAULICS
- Descriptors DEC
- DATA; DESIGN; EQUATIONS; FLUID MECHANICS; FUNCTIONS; HYDRAULICS; INFORMATION; MATHEMATICS; MECHANICS; NUMERICAL DATA; REACTIVITY COEFFICIENTS; REACTOR LIFE CYCLE; SIMULATION
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.