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.
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.
2024 journal article
ARTISANS-Artificial Intelligence for Simulation of Advanced Nuclear Systems for Nuclear Fission Technology
NUCLEAR ENGINEERING AND DESIGN, 423.
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.
2024 journal article
Design considerations and Monte Carlo criticality analysis of spiral plate heat for Molten Salt Reactors
PROGRESS IN NUCLEAR ENERGY, 173.
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.
2023 journal article
Deep generative modeling-based data augmentation with demonstration using the BFBT benchmark void fraction datasets
NUCLEAR ENGINEERING AND DESIGN, 415.
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.
2023 report
Inverse Uncertainty Quantification by Hierarchical Bayesian Modeling and Application in Nuclear System Thermal-Hydraulics Codes
(ArXiv Preprint No. 2305.16622).
2023 journal article
Prediction and uncertainty quantification of SAFARI-1 axial neutron flux profiles with neural networks
ANNALS OF NUCLEAR ENERGY, 188.
2023 journal article
Scalable Inverse Uncertainty Quantification by Hierarchical Bayesian Modeling and Variational Inference
ENERGIES, 16(22).
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.
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.
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.
2021 report
Structural Health Monitoring of Microreactor Safety Systems Using Convolutional Neural Networks
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.
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.
2020 journal article
Enhancing the One-Dimensional SFR Thermal Stratification Model via Advanced Inverse Uncertainty Quantification Methods
Nuclear Technology, 10, 1–19.
2020 journal article
System code evaluation of near-term accident tolerant claddings during pressurized water reactor station blackout accidents
NUCLEAR ENGINEERING AND DESIGN, 368.
2019 journal article
Demonstration of the relationship between sensitivity and identifiability for inverse uncertainty quantification
Journal of Computational Physics, 396, 12–30.
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
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 *
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 * *
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 * *
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.
Contributors: , T. Kozlowski * & H. Meidani * *
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
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
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
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
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 * *
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
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
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
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 * *
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
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 * *
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 * *
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
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
2014 report
Neutronics and Fuel Performance Evaluation of Accident Tolerant Fuel under Normal Operation Conditions
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
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
Updated: June 29th, 2019 11:25
2019 - present
2017 - 2019
Updated: October 11th, 2019 14:14
2013 - 2017
2011 - 2013
2007 - 2011
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