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 …

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

The oxidation rates of several nuclear-grade graphites, NBG-18, NBG-17, IG-110 and IG-11,
were measured in air using thermogravimetry. Kinetic parameters and oxidation behavior for …

This paper introduces a novel approach, developed through an academic and industrial
collaboration, to the thermal treatment of nuclear graphite waste arising as a result of reactor …

The effects of different parameters on oxidation rate are non-linear, interactive and
diversified in which the change of adequacy of O2 supply is an important indicator. The …

In this study, the oxidation characteristics of nuclear grade graphites IG-110, IG-430, Type A
(MA), Type B (MB), PGA, ATR-2E, G347A and G458A in air environments at temperatures …

The oxidation behavior of IG-110, a graphite core component, was investigated at
temperatures ranging from 400 to 1000° C in a 10 ppm Ar/O2 flow to simulate the oxidation …

Graphite is used in the cores of gas-cooled reactors as both the neutron moderator and a
structural material, and traditional and novel graphite materials are being studied worldwide …

The oxidation behaviors of the nuclear graphite being developed were investigated using
gas chromatograph at 873–1373 K. The oxidation experiments were carried out with the gas …

Nuclear graphite is widely used in traditional and advanced nuclear reactors. Especially in
High Temperature Gas-cooled Reactors (HTGRs), nuclear graphite is the main composition …