The reactor core, moderator and reflectors of a thermal spectrum advanced molten salt
reactor will constitute multi-tons of graphite. Porous reactor-grade graphite, if unprotected …

Abstract (Very) High temperature gas-cooled reactors (HTGRs) are one of the 4th-
generation nuclear reactors with high inherent safety. They use graphite materials as …

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 possibility and consequences of salt-infiltration in graphite must be evaluated for
graphite used in molten salt reactors (MSRs) and fluoride-salt-cooled high-temperature …

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 …

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

High-temperature gas-cooled reactors (HTGRs) in operation use tristructural isotropic
(TRISO) particles embedded in graphite and carbonized resin matrix to form the fuel …

Water ingress into cores of high temperature gas-cooled reactors (HTGRs) can cause
serious safety problems in graphitic components, especially for matrix graphite, which is …

Abstract The USA DOE Advanced Reactor Technologies (ART) graphite R&D program
supporting HTR design is one of the longest running nuclear graphite R&D programs …