36 results about "Nuclear graphite" patented technology

The invention provides a spherical graphite corpuscle compound carbon material, which is a compound graphite composed of spherical graphite with a clad sheet of nonferrous metal; the graphite that is almost the nuclear pure grade is adopted as the raw material, then a PCS system is utilized to collide, curl, knead, compact, conglobate and clad the graphite corpuscle for surface treatment, the rhombus crystal structure of the natural graphite is improved from 20 percent to about 80 percent, then nonferrous elements is clad or inserted into the interlamination of the spherical graphite crystal,the direction of the clad compound material is changed from uniform direction to random direction and the clad compound material has low specific area and high stacking density. The beneficial effectis that: the clad spherical graphite completely changes the crystal structure and microstructure of the natural graphite, and has large electrochemical capacity, good chemical and thermo-stability and high charge-discharge efficiency; meanwhile, the clad spherical graphite can not only be used as the cathode material of the lithium ionization cell but also can be used as the raw materials for isotropic high-end graphite products such as nuclear graphite; In addition, the production technology is simple, the cost is low and the performance is reliable.

The invention relates to a large-dimension nuclear graphite material for a reactor internal of a high-temperature gas cooled reactor and a preparation method. The method comprises the following stepsof: raw material selection, grinding, mixing-kneading, forming, roasting, 0 to 1 time of impregnation, and graphitization / nuclear-pure processing. The large-dimension nuclear graphite material is simple in process and convenient to operate and adopts little production equipment, so that cost is further reduced; the large-dimension nuclear graphite material is convenient to popularize and apply andis applicable to large-scale production; compared with the prior art, the provided product has a large scale and has neutron irradiation performance data.

A highly isotropic graphite useful for, inter alia, nuclear applications is disclosed, which has a ash content of less than 300 ppm and a boron equivalence of less than about 2 ppm without requiring a post graphitization purification step.

The invention discloses a graphene composite material and a preparation method thereof. The graphene composite material has a multi-level core shell coating structure, wherein the nanometer silicon isused as the core, the graphene is used as the first coating layer, the carbon is used as the second coating layer, the surface of the nanometer silicon is coated with the graphene, and the surface ofthe graphene is coated with the carbon. The graphene has high conductivity, mechanical strength and flexibility, and provides a conductive network, an elastic space and a folded structure for the nanometer silicon, thereby being good for inhibiting the damage caused by the volume expansion of the silicon; the carbon can maintain the internal structure stability of the composite material, and prevent the composite electrode material from agglomerating and falling down. The composite electrode material has better stability and conductivity performance when being used for a lithium ion battery.The preparation method is simple in reaction and easy to control, and has a extensive application prospect.

The invention relates to a three-dimensional graphene composite material with a core-shell structure for a capacitive desalination electrode and a preparation method thereof. The method uses metal-organic framework as the core and graphene as the shell; through the electrostatic interaction between a certain concentration of graphite oxide solution and the metal-organic framework at a certain temperature, the precursor of the three-dimensional composite material with a core-shell structure is formed; further carbonization, pickling A three-dimensional graphene composite material is obtained; the composite material, acetylene black and polytetrafluoroethylene emulsion are evenly mixed, coated on graphite paper, and dried to obtain a capacitive desalination electrode. The process of the invention is fast, simple, low in cost and can be produced in batches. The obtained electrode has high specific surface area, good conductivity and wettability, and has potential application prospects in capacitive desalination.

The invention discloses a nuclear graphite material preparation method including the following steps: (1) mixing and kneading; (2) grinding; (3) isostatic compaction; (4) roasting, to be more specific, baking treatment of the product obtained by the step (3) in an atmosphere furnace introduced with halogen or halogenated hydrocarbon at the treatment temperature of 800 to 1100 DEG C; (5) dipping; and (6) roasting; according to the method, in the roasting process, a halogen or halogenated hydrocarbon purified gas is introduced, a purification procedure is inserted in without reduction of the common preparation step, the cost of purification can be greatly reduced, in the roasting process, asphalt volatile components may cause many holes in graphite blocks, the holes greatly facilitate the purified gas to enter into the graphite blocks for purification so as to facilitate further purification of nuclear graphite blocks and great reduction of impurities and boron equivalent; the nuclear graphite material preparation method has the advantages of simple process, convenient operation, less production equipment, can further reduce the cost, and is convenient in popularization and application, and suitable for mass production.

The invention belongs to the technical field of nuclear power and particularly discloses a nuclear power plant metal graphite seal ring removal device, comprising a portal frame mounted on a seal channel, a lift bolt inserted in the portal frame, and a nut sleeving the lift bolt; the nut is arranged above the portal frame, the top of the lift bolt is inserted into the top of the portal frame, and the bottom of the lift bolt is arranged above a seal ring outer metal frame mounted in a ring groove of the seal channel. The nuclear power plant metal graphite seal ring removal device is simple and reliable in structure and allows seal rings of different sizes to be removed quickly, completely and safely, and the problem that removing in engineering is not easy is solved.

The invention provides a method for preparing a thin-walled graphitized carbon-wrapped metal core-shell structure material, comprising: a lignin-metal composite material preparation step, including using lignin resin as a carbon source, metal salt as a metal source, and hydrothermal Carry out carbonization to carbon source and metal source by method to obtain lignin-metal composite material; And carbonization step, comprise adopting inverse programmed temperature method to carry out carbonization treatment to described lignin-metal composite material, obtain thin-walled graphitization wrapping metal core-shell material , in which metal is the core and graphitized carbon is the shell. The invention provides a method for preparing a thin-wall graphitized carbon-wrapped metal core-shell structure material with simple operation and low cost, and the performance of the thin-wall graphitized carbon-wrapped metal core-shell structure material prepared by the method is improved.

The invention provides a method for measuring the dimensional change behavior of nuclear graphite in an irradiation environment by using ion beam irradiation, comprising the following steps: 1) being beneficial to ion beam irradiation of a nuclear graphite sample of a certain size, so that the irradiated nuclear graphite The shape of the sample changes; 2) measure the shape change, and use the performance characteristics of the nuclear graphite sample to calculate the size change of the nuclear graphite sample under the irradiation environment by mathematical methods; and 3) by controlling the change of the ion beam irradiation dose, And repeat the above process to obtain the size change behavior curve of the nuclear graphite sample under the irradiation environment. The method provided by the present invention has the advantages of low cost and short period compared with the method of testing in the material test pile, and can be used to optimize the production raw materials and process in the nuclear graphite research and development process, and can also be used as a quality control method for nuclear graphite. It can be used as a means of sampling and analyzing graphite core samples of active reactors, and has high economic value and good application prospects.

The invention provides a preparation method for high-density, large-size and ultra-fine-pore nuclear graphite materials for fused salt piles from coke aggregates 1-5 micrometers in size. The preparation method has the advantages that in the forming process, paste is compacted through vibration and ramming, calcination as well as temperature rise speeds and in-furnace temperature differences in thegraphitization process are controlled, and the shrinkage rate of graphite green bodies is further controlled, so that the technical problems that the smaller the average particle size of conventionalaggregates is, the larger the specific surface area and the surface energy of particles are, and the large-size nuclear graphite materials cannot be prepared are solved; multiple halogen gases are introduced as purification gases, and simultaneous purification in the graphitization process is realized; the method is clear in procedure, technically reliable and feasible, and suitable for large-scale production.