For subthermal neutron energies, polycrystalline graphite shows a larger total cross section than predicted by existing theoretical models. In order to investigate the origin of this discrepancy we measured the total cross section of graphite samples of three different origins, in the energy range from 0.001 to 10 eV. Different experimental arrangements and sample treatments were explored, to identify the effect of various experimental parameters on the total cross section measurement. The experiments showed that the increase in total cross section is due to neutrons scattered around the forward direction. We associate these small angle scattered neutrons (SANS) to the porous structure of graphite, and formulate a very simple model to compu...
Gilsocarbon graphite, as a neutron moderator and load-bearing component in the core of the UK fleet ...
The pore-level characterisation of nuclear graphite is critical for predicting reactor safety and fo...
Graphite will be used as a structural and moderator material in next-generation nuclear reactors. Wh...
At subthermal neutron energies, polycrystalline graphite shows a large total cross-section due to sm...
Small angle neutron scattering (SANS) measures porosity in nuclear graphites, including both open po...
International audienceThe present article studies the in situ evolution of the pore structure of com...
Graphite is one of the promising candidates to be used in the next-generation first breeder reactors...
International audienceImpurities in nuclear graphite can become neutron-activated during operation, ...
Microcracks in neutron-irradiated nuclear grade graphite have been examined in detail for the first ...
Nuclear Graphite is a complex material, and its microstructure depends strongly upon the starting ma...
International audienceDue to its excellent moderator and reflector qualities, graphite was used in C...
The default theory of radiation damage in graphite invokes Frenkel pair formation as the principal c...
International audienceIn a previous work [1] we elucidated the in situ evolution of the porosity of ...
International audienceFor several decades, graphite has been used in French gas-cooled nuclear react...
Gilsocarbon graphite, as a neutron moderator and load-bearing component in the core of the UK fleet ...
The pore-level characterisation of nuclear graphite is critical for predicting reactor safety and fo...
Graphite will be used as a structural and moderator material in next-generation nuclear reactors. Wh...
At subthermal neutron energies, polycrystalline graphite shows a large total cross-section due to sm...
Small angle neutron scattering (SANS) measures porosity in nuclear graphites, including both open po...
International audienceThe present article studies the in situ evolution of the pore structure of com...
Graphite is one of the promising candidates to be used in the next-generation first breeder reactors...
International audienceImpurities in nuclear graphite can become neutron-activated during operation, ...
Microcracks in neutron-irradiated nuclear grade graphite have been examined in detail for the first ...
Nuclear Graphite is a complex material, and its microstructure depends strongly upon the starting ma...
International audienceDue to its excellent moderator and reflector qualities, graphite was used in C...
The default theory of radiation damage in graphite invokes Frenkel pair formation as the principal c...
International audienceIn a previous work [1] we elucidated the in situ evolution of the porosity of ...
International audienceFor several decades, graphite has been used in French gas-cooled nuclear react...
Gilsocarbon graphite, as a neutron moderator and load-bearing component in the core of the UK fleet ...
The pore-level characterisation of nuclear graphite is critical for predicting reactor safety and fo...
Graphite will be used as a structural and moderator material in next-generation nuclear reactors. Wh...