Nuclear Engineering

Investigation of thermo-mechanical processing and mechanical properties of CoCrFeNiMn high entropy alloy for peripheral vascular stent application

Proceedings of the ASME 11th International Manufacturing Science and Engineering Conference, 2016, vol 1.

Impact of fuel thermal conductivity degradation on Doppler feedback during rod ejection accident

Nuclear Engineering and Design, 307, 339–353.

Benchmarking the NEM real-time core model for VVER-1000 simulator application - asymmetric core

Proceedings of the 24th International Conference on Nuclear Engineering, 2016, vol 5.

A method to improve the sensitivity of neutron porosity measurement based on D-T source

Journal of Natural Gas Science and Engineering, 33, 879–884.

A Phonon-based covariance methodology for ENDF S(alpha, beta) and thermal neutron inelastic scattering cross sections

Nuclear Science and Engineering, 184(1), 84–113.

3D in-core fuel management optimization for breed-and-burn reactors

Progress in Nuclear Energy, 88, 58–74.

Vapor shield models for fusion reactors plasma-facing components

Journal of Fusion Energy, 35(5), 786–794.

The role of interfacial reactions in determining plasma-liquid chemistry

Plasma Chemistry and Plasma Processing, 36(6), 1393–1415.

Properties of cellulose-soy protein blend biofibers regenerated from an amine/salt solvent system

Cellulose, 23(6), 3747–3759.

Evaluation of plastic zone development in WE43 magnesium alloy upon friction stir processing using finite element modeling

Materials Science & Engineering. A, Structural Materials: Properties, Microstructure and Processing, 673, 178–184.

Effect of friction stir processing on microstructure and mechanical properties of laser-processed Mg-4Y-3Nd alloy

Materials & Design, 110, 663–675.

Development, verification, and validation of a fuel thermal conductivity degradation model in CTF

Annals of Nuclear Energy, 97, 246–261.

Best estimate plus uncertainty analysis of departure from nucleate boiling limiting case with CASL core simulator VERA-CS in response to PWR main steam line break event

Nuclear Engineering and Design, 309, 8–22.

Grain boundary sliding mechanism during high temperature deformation of AZ31 Magnesium alloy

Materials Science & Engineering. A, Structural Materials: Properties, Microstructure and Processing, 669, 171–177.

Amorphization resistance of nano-engineered SiC under heavy ion irradiation

Journal of Nuclear Materials, 478, 310–314.

Addition of monovalent electrolytes to improve storage stability of freeze-dried protein formulations

Journal of Pharmaceutical Sciences, 105(2), 530–541.

Investigation of the d(gamma,n)p reaction for gamma beam monitoring at ELI-NP

Journal of Instrumentation, 11.

Gamma-ray mass attenuation coefficient and half value layer factor of some oxide glass shielding materials

Annals of Nuclear Energy, 96, 26–30.

Coupled MCNP6/CTF code: Development, testing, and application

Annals of Nuclear Energy, 96, 1–11.

Implementation of a portable hpge for field contamination assay

Health Physics (New York, N.Y.), 110(6), 571–579.