M. Griffiths

Accident tolerant fuels for LWRs: A perspective

Defect, surface and displacement-threshold properties of α-zirconium simulated with a many-body potential

Extreme grain refinement by severe plastic deformation: A wealth of challenging science

Rate-Based Construction of Kinetic Models for Complex Systems

Formation of polycyclic aromatic hydrocarbons and their growth to soot—a review of chemical reaction pathways

Structural materials for fission & fusion energy

Hierarchical and comparative kinetic modeling of laminar flame speeds of hydrocarbon and oxygenated fuels

Computer simulation of point defect properties in dilute Fe—Cu alloy using a many-body interatomic potential

Enhanced radiation tolerance of ultrafine grained Fe–Cr–Ni alloy

Detailed chemical kinetic models for the low-temperature combustion of hydrocarbons with application to gasoline and diesel fuel surrogates

Modeling irradiation growth of zirconium and its alloys

Recent progress in the development of diesel surrogate fuels

Materials challenges in nuclear energy

Microencapsulated fuel technology for commercial light water and advanced reactor application

Irradiation creep mechanisms: An experimental perspective

Microstructural aspects of accelerated deformation of Zircaloy nuclear reactor components during service

A review of microstructure evolution in zirconium alloys during irradiation

Displacement energies for Zr measured in a HVEM

Comments on precipitate stability in neutron-irradiated Zircaloy-4

Anisotropic distribution of dislocation loops in HVEM‐irradiated Zr

Electron damage in zirconium

Study of point defect mobilities in zirconium during electron irradiation in a high-voltage electron microscope

Grain boundary sinks in neutron-irradiated Zr and Zr-alloys

Construction automatique d'un mécanisme de réaction radicalaire

Evolution of microstructure in hcp metals during irradiation