International audienceFor the first time, chemical analyses using Atom Probe Tomography were performed on a bolt made of cold worked 316 austenitic stainless steel, extracted from the internal structures of a pressurized water reactor after 17 years of reactor service. The irradiation temperature of these samples was 633 K and the irradiation dose was estimated to 12 dpa (7.81 × 1025 neutrons.m−2, E > 1 MeV). The samples were analysed with a laser assisted tomographic atom probe. These analyses have shown that neutron irradiation has a strong effect on the intragranular distribution of solute atoms. A high number density (6 × 1023 m−3) of Ni–Si enriched and Cr–Fe depleted clusters was detected after irradiation. Mo and P segregations at the...
Internal structures of pressurized water reactors, made of 304 and 316 austenitic stainless steels, ...
The T91 grade and similar 9Cr tempered-martensitic steels (also known as ferritic-martensitic) are l...
In an effort to understand the effect of high dose neutron irradiation on fast reactor cladding cand...
International audienceFor the first time, chemical analyses using Atom Probe Tomography were perform...
International audienceFor the first time, chemical analyses using Atom Probe Tomography were perform...
A combined atom probe tomography and atom probe field ion microscopy study has been performed on a s...
International audienceMaterials of the core internals of pressurized water reactor (austenitic stain...
International audienceMaterials of the core internals of pressurized water reactor (austenitic stain...
International audienceMaterials of the core internals of pressurized water reactor (austenitic stain...
International audienceMaterials of the core internals of pressurized water reactor (austenitic stain...
Stainless steel (SS) is a well-known material for the internal parts of nuclear power plants. It is ...
Stainless steel (SS) is a well-known material for the internal parts of nuclear power plants. It is ...
Internal structures of pressurized water reactors, made of 304 and 316 austenitic stainless steels, ...
Internal structures of pressurized water reactors, made of 304 and 316 austenitic stainless steels, ...
Internal structures of pressurized water reactors, made of 304 and 316 austenitic stainless steels, ...
Internal structures of pressurized water reactors, made of 304 and 316 austenitic stainless steels, ...
The T91 grade and similar 9Cr tempered-martensitic steels (also known as ferritic-martensitic) are l...
In an effort to understand the effect of high dose neutron irradiation on fast reactor cladding cand...
International audienceFor the first time, chemical analyses using Atom Probe Tomography were perform...
International audienceFor the first time, chemical analyses using Atom Probe Tomography were perform...
A combined atom probe tomography and atom probe field ion microscopy study has been performed on a s...
International audienceMaterials of the core internals of pressurized water reactor (austenitic stain...
International audienceMaterials of the core internals of pressurized water reactor (austenitic stain...
International audienceMaterials of the core internals of pressurized water reactor (austenitic stain...
International audienceMaterials of the core internals of pressurized water reactor (austenitic stain...
Stainless steel (SS) is a well-known material for the internal parts of nuclear power plants. It is ...
Stainless steel (SS) is a well-known material for the internal parts of nuclear power plants. It is ...
Internal structures of pressurized water reactors, made of 304 and 316 austenitic stainless steels, ...
Internal structures of pressurized water reactors, made of 304 and 316 austenitic stainless steels, ...
Internal structures of pressurized water reactors, made of 304 and 316 austenitic stainless steels, ...
Internal structures of pressurized water reactors, made of 304 and 316 austenitic stainless steels, ...
The T91 grade and similar 9Cr tempered-martensitic steels (also known as ferritic-martensitic) are l...
In an effort to understand the effect of high dose neutron irradiation on fast reactor cladding cand...