Uncertainty Quantification with MCMC method and BFBT Data
Creators
- 1. Department of Nuclear, Plasma and Radiological Engineering University of Illinois at Urbana-Champaign Urbana, IL, 61801 (United States)
Description
The reliability of predictions of the system codes is closely related to the validation of their physical models. For example, the accuracy of void fraction prediction in a Boiling Water Reactor (BWR) using TRACE code depends on the uncertainties of closure relations developed for the two-phase flow models. This work focus on quantifying the uncertainties of two physical models, interfacial drag model and subcooled boiling model, using Markov Chain Monte Carlo (MCMC) method and BFBT experimental benchmark data. We applied the MCMC and MLE algorithms to BFBT benchmark data and estimated the uncertainty distribution of two model parameters: subcooled boiling heat transfer coefficient and interfacial drag (bubbly/slug rod bundle) coefficient. These algorithms tend to give various estimation results. Despite the differences in these algorithms, we find that the estimation results are consistent. After obtaining the uncertainty estimates, we validated the uncertainty estimates by applying the estimated distributions of model parameters to TRACE prediction. The new predictions succeed in reducing the void fraction prediction error, but it is not possible to eliminate all prediction error. We are only adjusting two model parameters, and there exists uncertainties in all model parameters. Application of the algorithms to other physical models and experimental data will be helpful for future work. (authors)
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 114
- Journal Issue
- 1
- Journal Page Range
- p. 921-923
- ISSN
- 0003-018X
Conference
- Title
- Annual Meeting of the American Nuclear Society
- Dates
- 12-16 Jun 2016
- Place
- New Orleans, LA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52032283
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; ALGORITHMS; BENCHMARKS; BWR TYPE REACTORS; CLOSURES; DISTRIBUTION; FLOW MODELS; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; MARKOV PROCESS; MONTE CARLO METHOD; RELIABILITY; SUBCOOLED BOILING; TWO-PHASE FLOW; VOID FRACTION
- Descriptors DEC
- BOILING; CALCULATION METHODS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; FUEL ASSEMBLIES; MATHEMATICAL LOGIC; MATHEMATICAL MODELS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTORS; STOCHASTIC PROCESSES; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs.; Available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 United States