Kriging-Based Inverse Uncertainty Quantification of BISON Fission Gas Release Model
Creators
- 1. Department of Nuclear, Plasma and Radiological Engineering University of Illinois at Urbana-Champaign 224 Talbot Laboratory, 104 South Wright Street, Urbana, Illinois, 61801 (United States)
Description
Nuclear reactor fuel performance analysis studies the thermo-mechanical behavior of fuel rods and verify their compliance with safety criteria under both normal operation and accidental conditions. One of the major concerns in fuel performance analysis is the behavior of the fission gases xenon and krypton in uranium dioxide fuel, which significantly affect the thermo-mechanical performance of the nuclear fuel rods employed in current LWRs. Previously, the modeling of fission gas release (FGR) in nuclear fuel performance codes have been relying on empirical models which are not applicable beyond their range of calibration. Recently a more efficient and flexible physics-based FGR and swelling model that can describe a wider range of reactor operation conditions have been implemented in fuel performance code BISON. In this work, we performed Bayesian calibration to inversely quantify the uncertainties associated with the 5 tuning parameters in BISON FGR model, based on the time-dependent FGR measurement data from Riso-AN3 benchmark. It takes around 1 hour and 40 minutes for BISON to simulate the Riso-AN3 benchmark with a moderate mesh size using 32 processors. As hundreds of thousands of BISON simulations are needed during Markov Chain Monte Carlo (MCMC) sampling, running BISON directly is not a viable solution. Therefore we propose to use Kriging-based metamodels to replace BISON during MCMC sampling. Surrogate model is an approximation of the input/output relation of a computer code/model. It is also called metamodel, response surface, emulator. Surrogate models usually take much less computational time than the original model (like BISON) while maintaining the input/output relation of the original model to a desirable accuracy. Constructing the metamodels normally requires small number of executions of the original model. Once validated, metamodels can be used to perform uncertainty and sensitivity analysis, Bayesian calibration, optimization, etc
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 116
- Journal Page Range
- p. 629-632
- ISSN
- 0003-018X
Conference
- Title
- 2017 Annual Meeting of the American Nuclear Society
- Dates
- 11-15 Jun 2017
- Place
- San Francisco, CA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52087884
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; CALIBRATION; COMPUTERIZED SIMULATION; FISSION PRODUCT RELEASE; FUEL RODS; KRIGING; KRYPTON; MARKOV PROCESS; MATERIAL BALANCE; MONTE CARLO METHOD; NUCLEAR FUELS; OPTIMIZATION; PERFORMANCE; REACTOR OPERATION; SAMPLING; SENSITIVITY ANALYSIS; STEADY-STATE CONDITIONS; TIME DEPENDENCE; URANIUM DIOXIDE; XENON
- Descriptors DEC
- ACTINIDE COMPOUNDS; CALCULATION METHODS; CHALCOGENIDES; ELEMENTS; ENERGY SOURCES; FLUIDS; FUEL ELEMENTS; FUELS; GASES; MATERIALS; MATHEMATICS; NONMETALS; OPERATION; OXIDES; OXYGEN COMPOUNDS; RARE GASES; REACTOR COMPONENTS; REACTOR LIFE CYCLE; REACTOR MATERIALS; SIMULATION; STATISTICS; STOCHASTIC PROCESSES; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- 8 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)