Dr. Xu Wu is an Assistant Professor at the Department of Nuclear Engineering of the North Carolina State University. his research interests include: (1) Calibration, Validation, Data Assimilation, Uncertainty and Sensitivity Analysis; (2) Computational Statistics, Reduced Order Modeling, Bayesian Inference and Model Inversion; (3) mathematical representations of model discrepancy to improve model predictive capabilities; (4) Physics-Informed Machine Learning, Deep Learning; (5) System Thermal-Hydraulics, Nuclear Fuel Performance Modeling, Multi-physics Coupled Simulation; (6) Accident Tolerant Fuels (ATFs) modeling, etc.
Works (30)
Updated: April 21st, 2023 07:05
2023 journal article
Prediction and uncertainty quantification of SAFARI-1 axial neutron flux profiles with neural networks
ANNALS OF NUCLEAR ENERGY, 188.
author keywords: Uncertainty quantification; Deep neural networks; Bayesian Neural Networks; Monte Carlo dropout
arxiv.org (repository)
Sources: ORCID, Web Of Science
Added: March 23, 2023
2022 journal article
Bayesian inverse uncertainty quantification of a MOOSE-based melt pool model for additive manufacturing using experimental data
ANNALS OF NUCLEAR ENERGY, 165.
author keywords: Inverse uncertainty quantification; Melt pool; Additive manufacturing
Sources: Web Of Science, ORCID
Added: November 29, 2021
2022 article
Quantification of Deep Neural Network Prediction Uncertainties for VVUQ of Machine Learning Models
Yaseen, M., & Wu, X. (2022, November 4). NUCLEAR SCIENCE AND ENGINEERING, Vol. 11.
author keywords: Uncertainty quantification; Deep Neural Network; Monte Carlo Dropout; Deep Ensemble; Bayesian Neural Network
Sources: ORCID, Web Of Science
Added: November 3, 2022
2021 journal article
A comprehensive survey of inverse uncertainty quantification of physical model parameters in nuclear system thermal-hydraulics codes
NUCLEAR ENGINEERING AND DESIGN, 384.
author keywords: Inverse uncertainty quantification; Calibration; Physical model parameters; Frequentist; Bayesian; Empirical
Sources: Web Of Science, ORCID
Added: November 1, 2021
2021 journal article
Application of Kriging and Variational Bayesian Monte Carlo method for improved prediction of doped UO2 fission gas release
ANNALS OF NUCLEAR ENERGY, 153.
author keywords: Doped fuel; Variational Bayesian Monte Carlo (VBMC); Bayesian inference; Kriging; Principal Component Analysis (PCA)
Sources: Web Of Science, ORCID
Added: February 15, 2021
2021 journal article
Enhancing the One-Dimensional SFR Thermal Stratification Model via Advanced Inverse Uncertainty Quantification Methods
Nuclear Technology, 10, 1–19.
author keywords: Thermal stratification; sodium-cooled fast reactor; sensitivity analysis; inverse uncertainty quantification
Source: ORCID
Added: October 17, 2020
2021 journal article
Towards improving the predictive capability of computer simulations by integrating inverse Uncertainty Quantification and quantitative validation with Bayesian hypothesis testing
NUCLEAR ENGINEERING AND DESIGN, 383.
author keywords: Inverse Uncertainty Quantification; Quantitative validation; Bayesian hypothesis testing; Bayes factor; ANS nuclear grand challenge
Sources: Web Of Science, ORCID
Added: October 12, 2021
2020 journal article
System code evaluation of near-term accident tolerant claddings during pressurized water reactor station blackout accidents
NUCLEAR ENGINEERING AND DESIGN, 368.
author keywords: Accident Tolerant Fuel; FeCrAl; Cr-coating; Station Blackout
Sources: Web Of Science, ORCID
Added: November 2, 2020
2019 journal article
Demonstration of the relationship between sensitivity and identifiability for inverse uncertainty quantification
Journal of Computational Physics, 396, 12–30.
author keywords: Inverse uncertainty quantification; Modular Bayesian approach; Identifiability; Sensitivity
Source: ORCID
Added: July 5, 2019
2019 journal article
Gaussian Process–Based Inverse Uncertainty Quantification for TRACE Physical Model Parameters Using Steady-State PSBT Benchmark
Nuclear Science and Engineering, 193(1-2), 100–114.
author keywords: Inverse uncertainty quantification; Gaussian process; physical model parameter uncertainty; PSBT benchmark
Source: ORCID
Added: July 5, 2019
2018 conference paper
Bayesian calibration and uncertainty quantification for trace based on PSBT benchmark
Transactions of the American Nuclear Society, 118, 419–422. http://www.scopus.com/inward/record.url?eid=2-s2.0-85062963843&partnerID=MN8TOARS
Source: ORCID
Added: July 5, 2019
2018 journal article
Inverse uncertainty quantification using the modular Bayesian approach based on Gaussian Process, Part 2: Application to TRACE
Nuclear Engineering and Design, 335, 417–431.
author keywords: Inverse uncertainty quantification; Bayesian calibration; Gaussian Process; Modular Bayesian; Model discrepancy
Source: ORCID
Added: July 5, 2019
2018 journal article
Inverse uncertainty quantification using the modular Bayesian approach based on Gaussian process, Part 1: Theory
Nuclear Engineering and Design, 335, 339–355.
author keywords: Inverse uncertainty quantification; Bayesian calibration; Gaussian process; Modular Bayesian; Model discrepancy
Source: ORCID
Added: July 5, 2019
2018 journal article
Kriging-based inverse uncertainty quantification of nuclear fuel performance code BISON fission gas release model using time series measurement data
Reliability Engineering and System Safety, 169, 422–436.
author keywords: Inverse uncertainty quantification; Metamodel; Kriging; Nuclear fuel performance analysis; Principal component analysis
Source: ORCID
Added: July 5, 2019
2018 conference paper
On the connection between sensitivity and identifiability for inverse uncertainty quantification
Transactions of the American Nuclear Society, 118, 411–414. http://www.scopus.com/inward/record.url?eid=2-s2.0-85062995468&partnerID=MN8TOARS
Source: ORCID
Added: July 5, 2019
2018 conference paper
Sensitivity and uncertainty analysis for fuel performance evaluation of Cr 2 O 3 -doped UO 2 fuel under LB-LOCA
Transactions of the American Nuclear Society, 119, 440–443. http://www.scopus.com/inward/record.url?eid=2-s2.0-85060860913&partnerID=MN8TOARS
Source: ORCID
Added: July 5, 2019
2018 conference paper
System code evaluation of accident tolerant claddings during BWR station blackout accident
Transactions of the American Nuclear Society, 119, 444–447. http://www.scopus.com/inward/record.url?eid=2-s2.0-85060862292&partnerID=MN8TOARS
Source: ORCID
Added: July 5, 2019
2018 conference paper
Validating trace void fraction predictive capability using the quantitative area validation metric
Transactions of the American Nuclear Society, 118, 423–426. http://www.scopus.com/inward/record.url?eid=2-s2.0-85062957450&partnerID=MN8TOARS
Source: ORCID
Added: July 5, 2019
2017 journal article
Inverse uncertainty quantification of TRACE physical model parameters using sparse gird stochastic collocation surrogate model
Nuclear Engineering and Design, 319, 185–200.
Source: ORCID
Added: July 5, 2019
2017 journal article
Inverse uncertainty quantification of reactor simulations under the Bayesian framework using surrogate models constructed by polynomial chaos expansion
Nuclear Engineering and Design, 313, 29–52.
Source: ORCID
Added: July 5, 2019
2017 conference paper
Kriging-based inverse uncertainty quantification of BISON fission gas release model
Transactions of the American Nuclear Society, 116, 629–632. http://www.scopus.com/inward/record.url?eid=2-s2.0-85033468956&partnerID=MN8TOARS
Source: ORCID
Added: July 5, 2019
2017 conference paper
Sensitivity and uncertainty analysis of TRACE Physical Model Parameters based on PSBT benchmark using Gaussian process emulator
17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, 2017-September. http://www.scopus.com/inward/record.url?eid=2-s2.0-85051935457&partnerID=MN8TOARS
Source: ORCID
Added: July 5, 2019
2017 conference paper
Surrogate-based inverse uncertainty quantification of TRACE physical model parameters using steady-state PSBT void fraction data
17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, 2017-September. http://www.scopus.com/inward/record.url?eid=2-s2.0-85051987392&partnerID=MN8TOARS
Source: ORCID
Added: July 5, 2019
2015 journal article
Coupling of system thermal-hydraulics and Monte-Carlo code: Convergence criteria and quantification of correlation between statistical uncertainty and coupled error
Annals of Nuclear Energy, 75, 377–387.
author keywords: Monte Carlo; System thermal-hydraulics; Coupled simulation; Uncertainty quantification
Source: ORCID
Added: July 5, 2019
2015 conference paper
Evaluation of accident tolerant FeCrAl coating for PWR cladding under normal operating conditions with coupled neutron transport and fuel performance
Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015, 3, 2334–2344. http://www.scopus.com/inward/record.url?eid=2-s2.0-84949522107&partnerID=MN8TOARS
Source: ORCID
Added: July 5, 2019
2015 journal article
Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions
Annals of Nuclear Energy, 85, 763–775.
author keywords: FeCrAl; Accident Tolerant Fuel
Source: ORCID
Added: July 5, 2019
2014 conference paper
Coupling of system thermal-hydraulics and monte-carlo method for a consistent thermal-hydraulics-reactor physics feedback
International Congress on Advances in Nuclear Power Plants, ICAPP 2014, 2, 1164–1174. http://www.scopus.com/inward/record.url?eid=2-s2.0-84907077778&partnerID=MN8TOARS
Source: ORCID
Added: July 5, 2019
2014 conference paper
Neutronics analysis of improved accident tolerance LWR fuel by modifing Zircaloy cladding of fuel pins
International Congress on Advances in Nuclear Power Plants, ICAPP 2014, 1, 159–166. http://www.scopus.com/inward/record.url?eid=2-s2.0-84907085456&partnerID=MN8TOARS
Source: ORCID
Added: July 5, 2019
2014 conference paper
Uncertainty quantification for coupled Monte Carlo and thermal-hydraulics codes
Transactions of the American Nuclear Society, 110, 189–191. http://www.scopus.com/inward/record.url?eid=2-s2.0-84904692027&partnerID=MN8TOARS
Source: ORCID
Added: July 5, 2019
2013 conference paper
Engineered Zircaloy cladding modifications for improved accident tolerance of LWR fuel: A summary
LWR Fuel Performance Meeting, Top Fuel 2013, 1, 56–58. http://www.scopus.com/inward/record.url?eid=2-s2.0-84902344678&partnerID=MN8TOARS
Source: ORCID
Added: July 5, 2019
Employment
Updated: June 29th, 2019 11:25
2019 - present
North Carolina State University Raleigh, NC, US
Assistant Professor
Department of Nuclear Engineering
2017 - 2019
Massachusetts Institute of Technology Cambridge, MA, US
Postdoctoral Associate
Department of Nuclear Science and Engineering
Education
Updated: October 11th, 2019 14:14
2013 - 2017
University of Illinois at Urbana-Champaign Urbana, IL, US
Ph.D
Department of Nuclear, Plasma and Radiological Engineering
2011 - 2013
University of Illinois at Urbana-Champaign Urbana, IL, US
M.S. in Nuclear Engineering
Department of Nuclear, Plasma and Radiological Engineering
2007 - 2011
Shanghai Jiao Tong University Shanghai, CN
B.S in Nuclear Engineering and Technology
School of Mechanical Engineering
