method for the manufacture of the product from the research graphite products

摘要

1,169,322. Neutron absorbing materials. COMMISSARIAT A L'ENERGIE ATOMIQUE. 13 March, 1968 [24 March, 1967], No. 12132/68. Heading G6R. A neutron absorbing material consists of a compact body of artificial graphite powder bound by coke resulting from the carbonization of pitch or coal tar, with a neutron absorbing compound selected from boron nitride, dehydrated borocalcite and oxides of rare earth metals dispersed throughout in powder form. The graphite powder can be made up of two parts, one having a particle size less than 80Á and the other a particle size within the range 0À5 to 1À5 mm. In order to facilitate subsequent extrusion, up to 10% by wt. of the graphite-neutron absorbing compound mixture may be replaced by lamp-black. The neutron absorbing compound has a particle size less than 80Á and the mixing operation is carried out in a heating mixer at a temperature between 100‹ and 150‹ C. in order to eliminate the water content. Once the compound has been completely dispersed, a binder such as coal-tar, pitch or petroleum asphalt in a proportion between 15% and 30% by wt. of the dry mixture is added to form a paste which is extruded or press-formed to the desired shape. It is then transferred to a furnace in which it is baked without exposure to air in order to carbonize the binder, preferably beneath a layer of coke powder, at a temperature below that at which reduction of the neutron absorbing compound by carbon takes place at an appreciable rate. This temperature should be in the range 900‹ to 1700‹ C., preferably between 1000‹ and 1200‹ C., but below 1150‹ C. in the case of borocalcite. The use of boron nitride enables a boron content as high as 15% by wt. to be attained whereas the use of the lower cost borocalcite does not result in a boron content greater than 6% by wt. Rare earth oxides permit the fabrication of parts which can be irradiated to very high doses since they do not give rise to helium evolution by the (n, ) reaction. The material may be used as a shield against fast neutrons or as a fast reactor control member. In the latter application, it is advantageous to employ oxides containing a high proportion of the rare earths which have a particularly high neutron capture cross-section, especially gadolinium oxide.