Xu Wu
Nuclear Engineering
Dr. Xu Wu is an Assistant Professor at the Department of Nuclear Engineering of the North Carolina State University. Dr. Wu received his B.S. degree in nuclear engineering from the Shanghai Jiao Tong University in China in 2011. He obtained his Ph.D. degree in nuclear engineering in 2017 from the University of Illinois at Urbana – Champaign. Prior to joining NCSU, he was a Postdoctoral Research Associate in the Department of Nuclear Science and Engineering at Massachusetts Institute of Technology. Dr. Wu is the principal investigator (PI) of the ARTISANS (ARTificial Intelligence for Simulation of Advanced Nuclear Systems) research group at NCSU-NE. The research in the ARTISANS group revolves around uncertainty quantification (UQ) and scientific machine learning (SciML). The goal is to combine SciML, experimentation and modeling & simulation (M&S) into a unified approach to improve the predictive capabilities of computer models and enable reduced reliance on expensive measurement data. Additionally, the application of such research will be focused on risk and economics evaluations of advanced nuclear reactors, such as small modular reactors and micro-reactors. The ultimate goal is to dramatically reduce the capital and operating costs of nuclear systems to maintain global technology leadership for nuclear energy.
Works (42)
Updated: December 23rd, 2024 12:15
2025 journal article
Hierarchical Bayesian modeling for Inverse Uncertainty Quantification of system thermal-hydraulics code using critical flow experimental data
International Journal of Heat and Mass Transfer.
Source: ORCID
Added: December 3, 2024
2024 journal article
A systematic approach for the adequacy analysis of a set of experimental databases: Application in the framework of the ATRIUM activity
NUCLEAR ENGINEERING AND DESIGN, 421.
author keywords: Adequacy analysis; Experimental databases; Representativeness analysis; Completeness analysis; Multicriteria decision problem; ATRIUM activity
Sources: Web Of Science, NC State University Libraries
Added: April 29, 2024
2024 journal article
ARTISANS-Artificial Intelligence for Simulation of Advanced Nuclear Systems for Nuclear Fission Technology
NUCLEAR ENGINEERING AND DESIGN, 423.
author keywords: Artificial intelligence; Machine learning; Nuclear fission technology; Advanced nuclear reactors
Sources: ORCID, Web Of Science, NC State University Libraries
Added: April 8, 2024
2024 journal article
Clustering and uncertainty analysis to improve the machine learning-based predictions of SAFARI-1 control follower assembly axial neutron flux profiles
ANNALS OF NUCLEAR ENERGY, 206.
author keywords: Deep Neural Networks; Uncertainty Quantification; Monte Carlo Dropout; Clustering analysis; Gaussian Process
open access via arxiv.org (repository)
Sources: ORCID, Web Of Science, NC State University Libraries
Added: June 1, 2024
2024 journal article
Design considerations and Monte Carlo criticality analysis of spiral plate heat for Molten Salt Reactors
PROGRESS IN NUCLEAR ENERGY, 173.
author keywords: Spiral plate heat exchanger; Monte Carlo; Criticality; Molten Salt Reactor
Sources: Web Of Science, NC State University Libraries
Added: July 17, 2024
2024 journal article
Functional PCA and deep neural networks-based Bayesian inverse uncertainty quantification with transient experimental data
COMPUTER METHODS IN APPLIED MECHANICS AND ENGINEERING, 420.
author keywords: Bayesian inverse UQ; Functional alignment; Functional PCA; Neural networks
TL;DR:
This work focuses on developing an inverse UQ process for time-dependent responses, using functional principal component analysis (PCA) and deep neural network (DNN)-based surrogate models, and shows an improvement in reducing the dimension of the TRACE transient simulations.
(via Semantic Scholar)
Sources: ORCID, Web Of Science, NC State University Libraries
Added: January 25, 2024
2023 journal article
Deep generative modeling-based data augmentation with demonstration using the BFBT benchmark void fraction datasets
NUCLEAR ENGINEERING AND DESIGN, 415.
author keywords: Deep generative modeling; Generative adversarial networks; Normalizing flows; Variational autoencoders
TL;DR:
The findings shows that DGMs have a great potential to augment scientific data in nuclear engineering, which proves effective for expanding the training dataset and enabling other DL models to be trained more accurately.
(via Semantic Scholar)
UN Sustainable Development Goal Categories
3. Good Health and Well-being
(Web of Science)
Sources: Web Of Science, NC State University Libraries, ORCID
Added: December 18, 2023
2023 journal article
Fast and accurate reduced-order modeling of a MOOSE-based additive manufacturing model with operator learning
INTERNATIONAL JOURNAL OF ADVANCED MANUFACTURING TECHNOLOGY, 129(7-8), 3123–3139.
author keywords: Additive manufacturing; Reduced-order modeling; Fourier neural operator; Deep operator network; MOOSE framework
Sources: Web Of Science, NC State University Libraries
Added: April 8, 2024
2023 report
Inverse Uncertainty Quantification by Hierarchical Bayesian Modeling and Application in Nuclear System Thermal-Hydraulics Codes
(ArXiv Preprint No. 2305.16622).
Sources: NC State University Libraries, NC State University Libraries
Added: September 14, 2023
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
TL;DR:
Deep Neural Networks are used to predict the assembly axial neutron flux profiles in the SAFARI-1 research reactor with quantified uncertainties in the ANN predictions and extrapolation to cycles not used in the training process, indicating good prediction and generalization capability.
(via Semantic Scholar)
UN Sustainable Development Goal Categories
11. Sustainable Cities and Communities
(Web of Science)
Sources: ORCID, Web Of Science, NC State University Libraries
Added: March 23, 2023
2023 journal article
Scalable Inverse Uncertainty Quantification by Hierarchical Bayesian Modeling and Variational Inference
ENERGIES, 16(22).
author keywords: inverse uncertainty quantification; hierarchical Bayesian; variational inference; nuclear thermal-hydraulics
Sources: Web Of Science, NC State University Libraries
Added: January 2, 2024
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
TL;DR:
Three techniques for UQ of DNNs are compared, namely, Monte Carlo Dropout, Deep Ensembles (DE), and Bayesian Neural Networks (BNNs), and it is found that the three methods typically require different DNN architectures and hyperparameters to optimize their performance.
(via Semantic Scholar)
UN Sustainable Development Goal Categories
11. Sustainable Cities and Communities
(Web of Science)
Sources: ORCID, Web Of Science, NC State University Libraries
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
TL;DR:
This review paper aims to provide a comprehensive and comparative discussion of the major aspects of the IUQ methodologies that have been used on the physical models in system thermal-hydraulics codes, including solidity, complexity, accessibility, independence, flexibility, comprehensiveness, transparency, and tractability.
(via Semantic Scholar)
UN Sustainable Development Goal Categories
11. Sustainable Cities and Communities
(Web of Science)
Sources: Web Of Science, NC State University Libraries
Added: November 1, 2021
2021 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
UN Sustainable Development Goal Categories
9. Industry, Innovation and Infrastructure
(Web of Science)
Sources: Web Of Science, NC State University Libraries
Added: November 29, 2021
2021 report
Structural Health Monitoring of Microreactor Safety Systems Using Convolutional Neural Networks
Sources: Crossref, NC State University Libraries
Added: June 24, 2023
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
TL;DR:
This paper proposes a comprehensive framework to integrate results from inverse UQ and quantitative validation to provide robust predictions to account for all available sources of uncertainties in a rigorous Uncertainty Quantification process.
(via Semantic Scholar)
UN Sustainable Development Goal Categories
11. Sustainable Cities and Communities
(Web of Science)
Sources: Web Of Science, NC State University Libraries
Added: October 12, 2021
2020 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)
TL;DR:
A novel optimization framework, Variational Bayesian Monte Carlo (VBMC) is demonstrated as a low-cost nonintrusive approach for Bayesian calibration and compared to the conventional statistical Markov Chain Monte Carlo sampling showing similar accuracy but superior efficiency.
(via Semantic Scholar)
UN Sustainable Development Goal Categories
11. Sustainable Cities and Communities
(Web of Science)
Sources: Web Of Science, NC State University Libraries
Added: February 15, 2021
2020 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
UN Sustainable Development Goal Categories
11. Sustainable Cities and Communities
(Web of Science)
Source: ORCID
Added: October 17, 2020
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
UN Sustainable Development Goal Categories
11. Sustainable Cities and Communities
(Web of Science)
Sources: Web Of Science, NC State University Libraries
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
TL;DR:
It is shown that identifiability is largely related to the sensitivity of the calibration parameters with regards to the chosen responses, and an improved modular Bayesian approach for inverse UQ is adopted that does not require priors for the model discrepancy term.
(via Semantic Scholar)
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
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.
Contributors: C. Wang *, * & T. Kozlowski *
author keywords: Inverse uncertainty quantification; Gaussian process; physical model parameter uncertainty; PSBT benchmark
TL;DR:
The issue of missing uncertainty information for physical model parameters in the thermal-hydraulic code TRACE is addressed with inverse uncertainty quantification (IUQ), using the steady-state void fraction experimental data in the Organisation for Economic Co-operation and Development/Nuclear Energy Agency PSBT (Pressurized water reactor Sub-channel and Bundle Tests benchmark).
(via Semantic Scholar)
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy
(OpenAlex)
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.
Contributors: * , T. Kozlowski *, H. Meidani * & K. Shirvan *
author keywords: Inverse uncertainty quantification; Bayesian calibration; Gaussian Process; Modular Bayesian; Model discrepancy
TL;DR:
This research addresses the “lack of input uncertainty information” issue for TRACE physical input parameters, which was usually ignored or described using expert opinion or user self-assessment in previous work.
(via Semantic Scholar)
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.
Contributors: * , T. Kozlowski *, H. Meidani * & K. Shirvan *
author keywords: Inverse uncertainty quantification; Bayesian calibration; Gaussian process; Modular Bayesian; Model discrepancy
TL;DR:
This paper used Bayesian analysis to establish the inverse UQ formulation, with systematic and rigorously derived metamodels constructed by Gaussian Process (GP), and proposed an improved modular Bayesian approach that can avoid extrapolating the model discrepancy that is learnt from the inverseUQ domain to the validation/prediction domain.
(via Semantic Scholar)
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 <inf>2</inf> O <inf>3</inf> -doped UO <inf>2</inf> 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.
Contributors: * , T. Mui *, G. Hu *, H. Meidani * & T. Kozlowski *
TL;DR:
This research solves the problem of lack of uncertainty information for TRACE physical model parameters for the closure relations by replacing such ad-hoc expert judgment with inverse Uncertainty Quantification (UQ) based on OECD/NRC BWR Full-size Fine-Mesh Bundle Tests (BFBT) benchmark steady-state void fraction data.
(via Semantic Scholar)
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 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.
Contributors: * , T. Kozlowski * & H. Meidani *
author keywords: Inverse uncertainty quantification; Metamodel; Kriging; Nuclear fuel performance analysis; Principal component analysis
TL;DR:
In this paper, inverse Uncertainty Quantification (UQ) under the Bayesian framework is applied to BISON code FGR model based on Riso-AN3 time series experimental data and the posterior distributions for the uncertain input factors can be used to replace the expert specifications for future uncertainty/sensitivity analysis.
(via Semantic Scholar)
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy
(OpenAlex)
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
2016 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.
Contributors: * & T. Kozlowski *
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.
Contributors: * , T. Kozlowski * & J. Hales *
author keywords: FeCrAl; Accident Tolerant Fuel
Source: ORCID
Added: July 5, 2019
2014 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.
Contributors: * & T. Kozlowski *
author keywords: Monte Carlo; System thermal-hydraulics; Coupled simulation; Uncertainty quantification
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy
(OpenAlex)
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 report
Neutronics and Fuel Performance Evaluation of Accident Tolerant Fuel under Normal Operation Conditions
Sources: Crossref, NC State University Libraries
Added: June 24, 2023
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
Contributors: B. Heuser, T. Kozlowski & W. Xu
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
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