Graphite ferric chloride, C₁₂FeCl₃, was prepared by heating anhydrous ferric chloride with graphite at 305°C. The purified compound containing 53% ferric chloride was not attacked by hot 6N hydrochloric acid or 6N sodium hydroxide solutions. X-ray diffraction measurements gave a powder pattern which was distinctly different from that of either graphite or ferric chloride and from which it was apparent that no free ferric chloride existed in the compound. The separation of the graphite layer-planes was increased from 3.36 to 9.4Å by the intercalation of the ferric chloride molecules. Tests for exchange between C₁₂FeCl₃ and Fe⁺⁺⁺ ion were made using radioactive Fe⁵⁹. In no instance was any measurable exchange observed. The compound was subje...
International audienceIn France, graphite is present as reflector, moderator or structural element i...
Ce travail s'inscrit dans le cadre des études sur la gestion des déchets graphités issus du démantèl...
Issues associated with handling irradiated graphite of uranium-graphite nuclear reactors are examine...
Graphite ferric chloride, C₁₂FeCl₃, was prepared by heating anhydrous ferric chloride with graphite ...
Isotherms of the ferric chloride-graphite system have been determined at 300°C, 310°C, and 350°C. It...
Progressive reduction of the stage-1 graphite intercalation compound, (GIC), C14FeCl3.04 using a sol...
The locations and the chemical forms (chemical bonds) of radionuclides in neutron-irradiated nuclear...
International audienceGraphite was used as a moderator in the French-designed first generation nucle...
Ce travail se situe dans le cadre des études sur la gestion des déchets graphites des centrales nucl...
We present here direct imaging, microdiffraction and microanalysis results on FeCl3 and CoCl2 G.I.C....
Searching for the chemical and catalytic properties of iron-graphite, we reduced stage-1 FeCl3-graph...
The intercalation compounds potassium graphite, graphite ferric chloride, graphite copper sulphide a...
International audienceThis paper presents a radioanalytical methodology and the main measurement res...
Presented at the NuMat 2014 Conference, 27–30 October 2014, Clearwater, Florida, USA.International a...
This work concerns the dismantling of the UNGG reactor which have produced around 23 000 t of graphi...
International audienceIn France, graphite is present as reflector, moderator or structural element i...
Ce travail s'inscrit dans le cadre des études sur la gestion des déchets graphités issus du démantèl...
Issues associated with handling irradiated graphite of uranium-graphite nuclear reactors are examine...
Graphite ferric chloride, C₁₂FeCl₃, was prepared by heating anhydrous ferric chloride with graphite ...
Isotherms of the ferric chloride-graphite system have been determined at 300°C, 310°C, and 350°C. It...
Progressive reduction of the stage-1 graphite intercalation compound, (GIC), C14FeCl3.04 using a sol...
The locations and the chemical forms (chemical bonds) of radionuclides in neutron-irradiated nuclear...
International audienceGraphite was used as a moderator in the French-designed first generation nucle...
Ce travail se situe dans le cadre des études sur la gestion des déchets graphites des centrales nucl...
We present here direct imaging, microdiffraction and microanalysis results on FeCl3 and CoCl2 G.I.C....
Searching for the chemical and catalytic properties of iron-graphite, we reduced stage-1 FeCl3-graph...
The intercalation compounds potassium graphite, graphite ferric chloride, graphite copper sulphide a...
International audienceThis paper presents a radioanalytical methodology and the main measurement res...
Presented at the NuMat 2014 Conference, 27–30 October 2014, Clearwater, Florida, USA.International a...
This work concerns the dismantling of the UNGG reactor which have produced around 23 000 t of graphi...
International audienceIn France, graphite is present as reflector, moderator or structural element i...
Ce travail s'inscrit dans le cadre des études sur la gestion des déchets graphités issus du démantèl...
Issues associated with handling irradiated graphite of uranium-graphite nuclear reactors are examine...