Nuclear Engineering

Characterization of Oxide Films on Alloys 600 and 690 Exposed to Supercritical and Subcritical Water

16th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. Presented at the 16th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Asheville, NC.

Fission Products in Nuclear Fuel: Comparison of Simulated Distribution with Correlative Characterization Techniques

Microscopy and Microanalysis, 19(S2), 968–969.

Transmission electron microscopy investigation of krypton bubbles in polycrystalline CeO2

Nuclear Technology, 182(2), 164–169. http://www.scopus.com/inward/record.url?eid=2-s2.0-84879071544&partnerID=MN8TOARS

Synthesis and structure-property relationships of a new family of layered carbides in Zr-Al(Si)-C and Hf-Al(Si)-C systems

Journal of the European Ceramic Society.

In situ TEM observation of dislocation evolution in Kr-irradiated UO 2 single crystal

Journal of Nuclear Materials, 443(1-3), 71–77.

Fission Products in Nuclear Fuel: Comparison of Simulated Distribution with Correlative Characterization Techniques

Nuclear science and technology made so simple, it belongs in your newspaper – popular science topics for the layman

https://www.amazon.com/Nuclear-Science-Technology-belongs-newspaper-ebook/dp/B00CC2KB5S

Characterization and evaluation of extended defects in CZT crystals for gamma-ray detectors

Journal of Crystal Growth, 379, 46–56.

Development of Cadmium Magnesium Telluride (Cd1−xMgxTe) for room temperature X- and gamma-ray detectors

Journal of Crystal Growth, 379, 34–40.

Post-growth thermal annealing study of CdZnTe for developing room-temperature X-ray and gamma-ray detectors

Journal of Crystal Growth, 379, 16–20.

Low-Temperature Photoluminescence Study of CdTe:In Crystals Annealed in Molten Bismuth

Journal of Electronic Materials, 42(11), 3138–3141.

‘Star-like’ defects in Cd-annealed CdZnTe crystals-an experimental study of their origin and formation mechanism

Crystal Research and Technology, 48(4), 221–226.

Friction Consolidation of MA956 powder

Journal of Nuclear Materials, 442(1-3), S112–S118.

Progress in the development of an implicit steady state solution in the coupled code TRACE/PARCS

Progress in Nuclear Energy, 66, 1–12.

High fidelity simulation of conventional and innovative LWR with the coupled Monte-Carlo thermal-hydraulic system MCNP-SUBCHANFLOW

Nuclear Engineering and Design, 262, 264–275.

Understanding using the Haling Power Depletion (HPD) as a guide for designing PWR cores

Annals of Nuclear Energy, 53, 120–128.

Uncertainty analysis of sub-channel code calculated ONB wall superheat in rod bundle experiments using the GRS methodology

Progress in Nuclear Energy, 65, 42–49.

A multi-scale homogenization and reconstruction approach for solid material temperature calculations in prismatic high temperature reactor cores

Nuclear Engineering and Design, 256, 1–13.

New developments of the MCNP/CTF/NEM/NJOY code system – Monte Carlo based coupled code for high accuracy modeling

Annals of Nuclear Energy, 51, 18–26.

Early Damage Mechanisms in Nuclear Grade Graphite under Irradiation

Materials Research Letters, 2(1), 43–50.