To evaluate the stability of nuclear materials in high temperature gas reactors under air ingress conditions, catalytic oxidation of IG-110 graphite by two simulated fission products, metallic Pd and Ag, was studied in oxidative atmosphere and at temperatures up to 1000 °C using an integrated furnace, mass spectroscopy and infrared spectroscopy system. Transmission electron microscopy and X-ray diffraction studies show that Pd and Ag nanoparticles were successfully introduced onto powdery IG-110 graphite through an impregnation and subsequent heat-treatment process. The combined mass spectroscopy and infrared spectroscopy methods allow simultaneous analysis of two gaseous products, CO and CO2, and separate measurements of activation energy ...
This study has investigated the laboratory scale thermal oxidation of nuclear graphite, as a proof-o...
Nuclear graphite is proposed for use in High-temperature Gas-cooled Reactor (HTGR) designs as the ne...
Nuclear graphite is proposed for use in High-temperature Gas-cooled Reactor (HTGR) designs as the ne...
The influence of three fission products Sr, Eu, and I on the oxidation of IG-110 nuclear graphite wa...
Nuclear graphite can be used in fission and fusion systems due to its excellent nuclear performance ...
Graphite is used in the gas-cooled nuclear reactors as both a neutron moderator and structural compo...
The oxidation kinetics of NBG-18 nuclear graphite was investigated between 500 and 775°C with oxygen...
The oxidation kinetics of NBG-18 nuclear graphite was investigated between 500 and 775°C with oxygen...
The oxidation kinetics of NBG-18 nuclear graphite was investigated between 500 and 775°C with oxygen...
The oxidation kinetics of NBG-18 nuclear graphite was investigated between 500 and 775°C with oxygen...
Gilsocarbon is a graphite grade used as a main structural proponent of the current UK fleet of Advan...
In this study, the oxidation characteristics of nuclear grade graphites IG-110, IG-430, Type A(MA), ...
Graphite IG-110 is a nuclear graphite structural and moderator material that has been used for high ...
In this study, the oxidation characteristics of nuclear grade graphites IG-110, IG-430, Type A(MA), ...
High-purity, nuclear-grade graphites react very slowly with oxygen and are noncombustible by convent...
This study has investigated the laboratory scale thermal oxidation of nuclear graphite, as a proof-o...
Nuclear graphite is proposed for use in High-temperature Gas-cooled Reactor (HTGR) designs as the ne...
Nuclear graphite is proposed for use in High-temperature Gas-cooled Reactor (HTGR) designs as the ne...
The influence of three fission products Sr, Eu, and I on the oxidation of IG-110 nuclear graphite wa...
Nuclear graphite can be used in fission and fusion systems due to its excellent nuclear performance ...
Graphite is used in the gas-cooled nuclear reactors as both a neutron moderator and structural compo...
The oxidation kinetics of NBG-18 nuclear graphite was investigated between 500 and 775°C with oxygen...
The oxidation kinetics of NBG-18 nuclear graphite was investigated between 500 and 775°C with oxygen...
The oxidation kinetics of NBG-18 nuclear graphite was investigated between 500 and 775°C with oxygen...
The oxidation kinetics of NBG-18 nuclear graphite was investigated between 500 and 775°C with oxygen...
Gilsocarbon is a graphite grade used as a main structural proponent of the current UK fleet of Advan...
In this study, the oxidation characteristics of nuclear grade graphites IG-110, IG-430, Type A(MA), ...
Graphite IG-110 is a nuclear graphite structural and moderator material that has been used for high ...
In this study, the oxidation characteristics of nuclear grade graphites IG-110, IG-430, Type A(MA), ...
High-purity, nuclear-grade graphites react very slowly with oxygen and are noncombustible by convent...
This study has investigated the laboratory scale thermal oxidation of nuclear graphite, as a proof-o...
Nuclear graphite is proposed for use in High-temperature Gas-cooled Reactor (HTGR) designs as the ne...
Nuclear graphite is proposed for use in High-temperature Gas-cooled Reactor (HTGR) designs as the ne...