Nuclear Engineering

Effect of dose on irradiation-induced loop density and Burgers vector in ion-irradiated ferritic/martensitic steel HT9

Philosophical Magazine, 98(26), 2440–2456.

The IAEA CRP on HTGR uncertainties: Sensitivity study of PHISICS/RELAP5-3D MHTGR-350 core calculations using various SCALE/NEWT cross-section sets for Ex. II-1a

Nuclear Engineering and Design, 329, 156–166.

Validation and Uncertainty Quantification for Wall Boiling Closure Relations in Multiphase-CFD Solver

Nuclear Science and Engineering, 193(1-2), 81–99.

Passive one-dimensional self-transmission imaging of subcritical metallic plutonium assemblies

Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 903, 277–286.

Digital pulse deconvolution with adaptive shaping for real-time high-resolution high-throughput gamma spectroscopy

Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment.

Investigation of a model based reconstruction technique for neutron tomography at the PULSTAR reactor

Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment.

Enhanced ductility in dynamic strain aging regime in a Fe-25Ni-20Cr austenitic stainless steel

Materials Science and Engineering: A, 729, 157–160.

Interface Tracking Investigation of Geometric Effects on the Bubbly Flow in PWR Subchannels

Nuclear Science and Engineering, 193(1-2), 46–62.

American National Standard Instrumentation and Systems for Monitoring Airborne Radioactivity

Grain size and density separation effects on luminescence dose estimates using brick material

Embedded Topical Meeting - Advances in Nuclear Nonproliferation Technology and Policy Conference 2018, ANTPC 2018, 192–195. http://www.scopus.com/inward/record.url?eid=2-s2.0-85067121319&partnerID=MN8TOARS

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

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

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

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.

Inverse uncertainty quantification using the modular Bayesian approach based on Gaussian process, Part 1: Theory

Nuclear Engineering and Design, 335, 339–355.

Inverse uncertainty quantification using the modular Bayesian approach based on Gaussian Process, Part 2: Application to TRACE

Nuclear Engineering and Design, 335, 417–431.

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

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

Development, verification and application of a new model for active nucleation site density in boiling systems

Nuclear Engineering and Design, 328, 1–9.

Two-Level Transport Methods with Independent Discretization

JOURNAL OF COMPUTATIONAL AND THEORETICAL TRANSPORT, 47(4-6), 424–450.