2022 journal article

Bayesian inverse uncertainty quantification of a MOOSE-based melt pool model for additive manufacturing using experimental data

*ANNALS OF NUCLEAR ENERGY*, *1*.

Sources: Web Of Science, ORCID

Added: November 29, 2021

2021 journal article

A comprehensive survey of inverse uncertainty quantification of physical model parameters in nuclear system thermal-hydraulics codes

*NUCLEAR ENGINEERING AND DESIGN*, *12*.

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*.

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.

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*, *11*.

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*.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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*.

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*.

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.

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.

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.

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.

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.

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.

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.

Source: ORCID

Added: July 5, 2019

2019 - present

2017 - 2019

2013 - 2017

2011 - 2013

2007 - 2011