A natural graphite recommended for use in nuclear applications was analyzed using thermogravimetric analysis. The oxidation behaviour was unlike that expected for flake-like particles. The dynamic data displayed an apparent bimodal reaction rate curve as a function of temperature and degree of conversion. Nevertheless, it was possible to model this behaviour with a single rate constant, i.e. without the need for a parallel reaction type of kinetic mechanism. The approach used in this paper to model the gas-solid reaction of graphite and oxygen, provides a consistent framework to test the validity of complementary isothermal and non-isothermal data for a specific solid state reaction
Chemical-looping combustion (CLC) provides a platform to generate energy streams while mitigating CO...
Graphite is used in the gas-cooled nuclear reactors as both a neutron moderator and structural compo...
In connection with analyses of severe air ingress accidents in high temperature gas-cooled reactors,...
An intrinsic mathematical model is developed for the investigation of the gas-solid reaction kinetic...
The oxidation kinetics of NBG-18 nuclear graphite was investigated between 500 and 775°C with oxygen...
A novel transient thermal analysis for oxidation was developed in order to predict mass loss during ...
High-purity, nuclear-grade graphites react very slowly with oxygen and are noncombustible by convent...
A kinetic study was conducted to provide information on oxidation of reactor graphites in the temper...
Nuclear graphite can be used in fission and fusion systems due to its excellent nuclear performance ...
Dissertation supervisor: Dr. Tushar K. Ghosh nad Dr. Sudarshan K. Loyalka.Includes vita.One of the m...
The influence of three fission products Sr, Eu, and I on the oxidation of IG-110 nuclear graphite wa...
The first generation of UK research and production reactors were graphite moderated and operated at ...
A test methodology has been defined in order to assess the risk of bulk-oxidation of nuclear graphit...
<p>Relative reaction rates between different oxidising gases and graphite at 0.1 atm and 800°C [<a h...
Chemical-looping combustion (CLC) provides a platform to generate energy streams while mitigating CO...
Chemical-looping combustion (CLC) provides a platform to generate energy streams while mitigating CO...
Graphite is used in the gas-cooled nuclear reactors as both a neutron moderator and structural compo...
In connection with analyses of severe air ingress accidents in high temperature gas-cooled reactors,...
An intrinsic mathematical model is developed for the investigation of the gas-solid reaction kinetic...
The oxidation kinetics of NBG-18 nuclear graphite was investigated between 500 and 775°C with oxygen...
A novel transient thermal analysis for oxidation was developed in order to predict mass loss during ...
High-purity, nuclear-grade graphites react very slowly with oxygen and are noncombustible by convent...
A kinetic study was conducted to provide information on oxidation of reactor graphites in the temper...
Nuclear graphite can be used in fission and fusion systems due to its excellent nuclear performance ...
Dissertation supervisor: Dr. Tushar K. Ghosh nad Dr. Sudarshan K. Loyalka.Includes vita.One of the m...
The influence of three fission products Sr, Eu, and I on the oxidation of IG-110 nuclear graphite wa...
The first generation of UK research and production reactors were graphite moderated and operated at ...
A test methodology has been defined in order to assess the risk of bulk-oxidation of nuclear graphit...
<p>Relative reaction rates between different oxidising gases and graphite at 0.1 atm and 800°C [<a h...
Chemical-looping combustion (CLC) provides a platform to generate energy streams while mitigating CO...
Chemical-looping combustion (CLC) provides a platform to generate energy streams while mitigating CO...
Graphite is used in the gas-cooled nuclear reactors as both a neutron moderator and structural compo...
In connection with analyses of severe air ingress accidents in high temperature gas-cooled reactors,...