Two distinct but interconnected approaches can be used to model diffusion in fluids; the first
focuses on dynamics of an individual particle, while the second deals with collective …

Thermal oxidation of nuclear graphite components is highly undesirable because it can
cause structural and property degradation that negatively affect a reactor's intended …

Abstract Beginning with Chicago Pile I, graphite has been used as a moderator material in
nuclear power stations and is considered a potential material for use in future Generation IV …

This work compared the 3D Random Pore Model (3D-RPM) with experimental and
characterization data to systematically study the effect of nuclear graphite microstructure and …

The modular high temperature reactor is a leading candidate for near-term deployment of an
advanced reactor concept. The US Department of Energy supports the development of high …

The acute oxidation behaviors for a number of nuclear graphite grades pertinent to gas-
cooled high-temperature reactor (HTR) designs are compared using established American …

Reactive surface area and its evolution play an important role in the oxidation behavior of
porous carbon materials. Here, the evolution of reactive surface area within nuclear graphite …

The oxidized residual strength for two nuclear graphite grades, fine-grained IG-110 and
medium-grained NBG-18, were determined over a mass loss range of 0% to 10% for three …

Measurements of nitrogen diffusion coefficient in graphene oxide (GO) and reduced
graphene oxide (rGO) have been performed at different temperatures ranging between 21° …

Oxidation of graphite components could influence their designed life in a high-temperature
nuclear reactor. The oxidized regions could potentially lower the allowed stress capacity …