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Title: Demonstration of emulator-based Bayesian calibration of safety analysis codes: Theory and formulation

Journal Article · · Science and Technology of Nuclear Installations
DOI:https://doi.org/10.1155/2015/839249· OSTI ID:1223307
 [1]; ORCiD logo [2];  [3]
  1. Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); FPoliSolutions, LLC, Murrysville, PA (United States)
  2. Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
  3. Idaho National Lab. (INL), Idaho Falls, ID (United States)

System codes for simulation of safety performance of nuclear plants may contain parameters whose values are not known very accurately. New information from tests or operating experience is incorporated into safety codes by a process known as calibration, which reduces uncertainty in the output of the code and thereby improves its support for decision-making. The work reported here implements several improvements on classic calibration techniques afforded by modern analysis techniques. The key innovation has come from development of code surrogate model (or code emulator) construction and prediction algorithms. Use of a fast emulator makes the calibration processes used here with Markov Chain Monte Carlo (MCMC) sampling feasible. This study uses Gaussian Process (GP) based emulators, which have been used previously to emulate computer codes in the nuclear field. The present work describes the formulation of an emulator that incorporates GPs into a factor analysis-type or pattern recognition-type model. This “function factorization” Gaussian Process (FFGP) model allows overcoming limitations present in standard GP emulators, thereby improving both accuracy and speed of the emulator-based calibration process. Calibration of a friction-factor example using a Method of Manufactured Solution is performed to illustrate key properties of the FFGP based process.

Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
1223307
Journal Information:
Science and Technology of Nuclear Installations, Vol. 2015; ISSN 1687-6075
Publisher:
HindawiCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 6 works
Citation information provided by
Web of Science

References (11)

Bayesian inference in probabilistic risk assessment—The current state of the art journal February 2009
Computer Model Calibration Using High-Dimensional Output journal June 2008
Variable Selection for Gaussian Process Models in Computer Experiments journal November 2006
Quantifying reactor safety margins Part 5: Evaluation of scale-up capabilities of best estimate codes journal May 1990
Application of fractional scaling analysis (FSA) to loss of coolant accidents (LOCA) journal September 2007
The dangers of sparse sampling for the quantification of margin and uncertainty journal September 2011
Design and Analysis of Computer Experiments journal November 1989
Screening, Predicting, and Computer Experiments journal February 1992
Statistics for Spatial Data book September 1993
Bayesian calibration of computer models journal August 2001
An Adaptive Metropolis Algorithm journal April 2001

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