36 results about "MOX fuel" patented technology

The invention relates to a process for preparing a castable powder of uranium dioxide UO2, for use in the manufacture of MOX fuel.This process comprises the following stages:1) to prepare an aqueous suspension of a powder of UO2 obtained by dry process from uranium hexafluoride, said suspension comprising 50 to 80% by weight of UO2 and at least one additive chosen among deflocculation agents, organic binders, hydrogen peroxide H2O2 and a powder of U3O8, in such a quantity that the viscosity of the suspension does not exceed 250 mPa.sec, and2) to atomise this suspension and dry it in a hot gas, at a temperature of 150 to 300° C., to obtain a castable powder of UO2 with an average particle size of 20 to 100 mum.

A method for carrying out a comprehensive quality control of MOX fuel rods, including measurement of plutonium content of pellets contained in the rod, check of internal structure and constituents in the rod, including the detection of rogue pellets, and measurement of dimensional characteristics and radioactive contamination along the rod surface, by moving the fuel rod axially, performing concurrently the measurements and checks along the fuel rod moved axially, using radiometry and radiography. An apparatus for carrying out the method.

The invention provides an estimation method for a critical accident environment release source item of MOX fuel. The method comprises the following steps: (1) determining the total number of fissures;(2) determining the release of aerosol; (3) determining the release of inert gas and radioactive iodine; (4) determining the influence of ventilation and exhaust equipment and purification measures;And (5) calculating the critical accident radiation quantity. The method provided by the invention can estimate the critical accident release amount of the MOX fuel.

This invention relates to a MOX fuel assembly for PWRs that enables satisfactorily suppressing a power peaking factor without the necessity of reducing the Pu content per fuel assembly. The MOX fuel assembly has a lattice arrangement in which one or more burnable poison contained UO₂ fuel rods and a plurality of MOX fuel rods are disposed in an n-rows by n-columns (n×n) lattice array. The MOX fuel rod consists of at least two kinds of MOX fuel rods including a plurality of first MOX fuel rods and a plurality of second MOX fuel rods. The first MOX fuel rod has a predetermined Pu content and a predetermined Pu weight, and the second MOX fuel rod has substantially the same Pu content as that of the first MOX fuel rod and a different Pu weight from that of the first MOX fuel rod.

The invention relates to a conveying container of a fuel component, in particular to a conveying container for a fast reactor MOX fuel component. The conveying container structurally comprises a cylinder body component, wherein a middle penetrating component used for accommodating the fuel component is arranged in the cylinder body component; a compression end cover is arranged on the end part of the cylinder body component; the cylinder body component comprises an inner cylinder, a middle cylinder and an outer cylinder; the compression end cover is divided into two layers; the first layer of compression end cover is fixedly connected with the inner cylinder of the cylinder body component to form a first layer of containing boundary of radioactive substances; the second layer of compression end cover is fixedly connected with the middle cylinder of the cylinder body component to form a second layer of containing boundary of the radioactive substances; a shielding body and a heat isolating layer are arranged between the middle cylinder and the outer cylinder. The conveying container has better shielding property, containing property, buffering property and heat isolating property; the requirement on transportation of the radioactive substances by regulations can be met; in the whole transportation process, the MOX fuel component can be kept in a subcritical state.

The invention belongs to the technical field of nuclear chemical radiation protection and in particular relates to a radiation protection method for an MOX pellet preparation process. Key equipment ona production line is enclosed by using glove boxes; the whole production line is formed by sequentially connecting a plurality of glove boxes; radioactive aerosol is used as an atmosphere in each glove box; each glove box is matched with an independent mechanical pump; the front end of the mechanical pump is designed to be provided with a filter-cloth-type efficient dust filter; the mechanical pump has the effect of making the average pressure inside each glove box smaller than the normal atmosphere pressure 300kPa; the glove box with the highest radiation level is placed in the middle of theproduction line; the radiation level of the glove box closer to the outer side is lower; the pressure of the glove box with a higher radiation level is lower; the pressure difference of the adjacentglove boxes is 20kPa; a sealing door with a sealing ring is designed at a junction between every two glove boxes; and the sealing door is closed under the condition that materials are not transferred.A whole set of radiation protection, detection and dirt removal method is established, the safety production of MOX fuel pellets is realized, and the safety of production operating personnel is guaranteed.

The invention relates to an MOX fuel component for evolving and flattening power and a method of flattening power. The component comprises doped fuel rods, fuel rods and guide tubes, wherein the doped fuel rods are fuel rods doped with long-life sub-actinide nuclides; the doped fuel rods, the fuel rods and the guide tubes form an array, and each doped fuel rod is adjacent to one of the guide tubes. In the MOX fuel component, the fuel rods adjacent to the guide tubes are installed as the doped fuel rods, and the long-life sub-actinide nuclides in the doped fuel rods are evolved in the neutron field, thereby reducing the costs and difficulty of final treatment of spent fuel. At the same time, the fission reaction rate of the doped fuel rods is reduced to lower the original high power around the guide tubes in the MOX fuel component, thereby achieving the effects of flattening the power of the MOX fuel component and enhancing the safety of a reactor core.

The invention discloses an MOX (Mixed Oxide) fuel assembly structure suitable for a supercritical water reactor, belonging to the field of nuclear power generation. A plurality of water boxes are formed into a square shell, a plurality of water rods are arranged in the shell formed by the water boxes, an MOX fuel rod with the diameter of R is arranged in a gap between every two adjacent water rods, the water rods include large water rods and small water rods, the cross section of each large water rod is of a square with the length of 3R and the width of 3R, the cross section of each small water rod is of a rectangle with the length of 3R and the width of R, gaps between every two adjacent water rods and between each water rod and each water box are both R and filled by the MOX fuel rods which are tidily arranged, and gaps between the MOX fuel rods and the water rods or between the MOX fuel rods and the inner walls of the water boxes form a fuel agent cooling channel. By using the MOX assembly structure is adopted in the supercritical water reactor, the same effects with the traditional structure in which only a UO2 assembly design is used can be achieved, and the condition of uneven power distribution factors of an assembly can be improved. The MOX fuel assembly structure has the characteristics of simple structure and little improvement on the traditional supercritical water reactor assembly and can be used for improving the safety of the reactor.

The invention relates to a method for loading an MOX fuel assembly arranged at multiple sub-regions in the radial direction. The MOX fuel assembly is arranged at the multiple sub-regions in the radial direction, the Pu content at each sub-region is designed and loaded, the Pu content of fuel pellets at the external sub-regions of the assembly is lower than that of fuel pellets at the internal sub-regions of the assembly, and it is guaranteed that the average Pu content of the assembly meets the designing requirement; meanwhile, fuel manufacturing difficulty caused by the type of the fuel pellets is considered to reduce a large core power peak factor, caused by an energy spectrum interference effect between the MOX fuel assembly and a UO2 fuel assembly, at the interface of the MOX fuel assembly and the UO2 fuel assembly, a brand-new MOX fuel assembly radial loading design is achieved, and the performance of the fuel assembly is improved.

The invention provides a recycling method for MOX pellets. The method comprises the following steps: step 1, selecting MOX fuel pellets, and analyzing and detecting appearances, sizes, uranium plutonium contents, impurity contents, O/M and density data; step 2, recycling pellets with unqualified O/M; step 3, recycling pellets with unqualified densities; step 4, recycling pellets with unqualified outer diameters; and step 5, recycling pellets with a plurality of unqualified indexes.

The invention belongs to the technical field of nuclear fuel production waste processing, and particularly relates to an MOX waste core block crushing device. The lower end of a spiral feeding mechanism is connected with the upper end of a material collection device shell. The upper end of a double-roller shell is connected with the lower end of the material collection device shell. Double rollersare located in the double-roller shell. The upper end of a fixed cone is connected with the lower end of the double-roller shell. A movable cone is arranged in the fixed cone. An eccentric shaft is inserted in the movable cone. The center axis of the movable cone does not coincide with the center axis of the eccentric shaft. The eccentric shaft is matched with a transmission shaft through a gear.The transmission shaft is connected with a transmission motor A through a coupling. The lower end of the fixed cone is connected with a material collection shell with the bottom face inclined. The eccentric shaft penetrates the material collection shell. The lower end of the material collection shell is connected with a material collection container. The material collection container is arrangedon a lifting rack. The double rollers are made to move oppositely at different rotating speeds by a transmission motor B through a gear set. By means of the MOX waste core block crushing device, unqualified MOX fuel core blocks subjected to sintering are crushed into powder particles which are of a certain particle size and certain particle size uniformity, and the MOX raw material recycling requirement is met.

The invention discloses a tube-in-tube type MA transmutation rod for a fast neutron reactor. The tube-in-tube type MA transmutation rod comprises a central layer which is externally provided with at least one outer layer in a surrounding manner, wherein the central layer is an MA nuclide tube, and the outer layer is a 6LiD nuclide tube, or the central layer is an MOX nuclide tube, and the outer layer is the MA nuclide tube and/or the 6LiD nuclide tube. According to the tube-in-tube type MA transmutation rod for the fast neutron reactor, a thermal fast neutron conversion material 6LiD is creatively added into the structural design of the MA transmutation rod. The invention provides three schemes of the basic structure of the transmutation rod, namely (1) a 6LiD/MA tube-in-tube type transmutation rod; (2) a 6LID/MA/MOX tube-in-tube type transmutation rod; and (3) an MA/MOX tube-in-tube type transmutation rod. The thicknesses of the tube walls of 6LiD, MA and MOX fuel in each scheme are continuously optimized, so a novel transmutation rod structure for disposing MA nuclide is provided, and the transmutation rate of the transmutation rod containing MA nuclide is improved.

The invention provides an MOX fuel rod end plug marking method, which comprises the steps: cleaning an end plug; marking a digital code; and marking bar code, and carrying out other steps. According to the invention, the digital code and the bar code are marked on the MOX fuel rod end plug at the same time, so that automatic recording of coded information in the fuel rod production process is achieved under the hot chamber shielding condition that manual intervention is inconvenient and direct, production information recording and material tracking are facilitated, the material circulation efficiency of the MOX fuel rod production line is improved, and the production efficiency is indirectly improved.

The invention relates to a loading method for MOX fuel assemblies axially arranged in multiple zones. The MOX fuel assemblies are arranged in multiple zones in the axial direction, the Pu content in each zone is subjected to loading design, the Pu content of fuel pellets in the upper zones of the assemblies is increased, and the Pu content of fuel pellets in the lower zones of the assemblies is decreased, so that it is guaranteed that the average Pu content of the assemblies meets design requirements, and meanwhile it is avoided that positive axial power offset at the beginning of the fuel cycle life is caused when the average Pu content does not meet design requirements. On the basis that the axial power offset is relieved, the fewest types of Pu content fuel pellets are adopted to achieve axial loading design of the MOX fuel assemblies.

A fuel assembly capable of linearizing change of an infinite multiplication factor of a fuel and flattening excess reactivity while increasing average fissile plutonium enrichment of a MOX fuel, and a reactor loaded with the fuel assembly can be provided. A fuel assembly includes first fuel rods containing Pu and not containing burnable poison, a second fuel rod containing uranium and burnable poison and not containing Pu, a water rod, and a channel box accommodating the first and second fuel rods and the water rod in a bundle. The second fuel rod is disposed on an outermost periphery and/or adjacent to the water rod, of a fuel rod array in a horizontal section, N2<N1 (N2 is a positive integer including zero) is satisfied where the number of the second fuel rods arranged on the outermost periphery is N1 and the number of the second fuel rods arranged adjacent to the water rod is N2, and W2<N2+W0<W1 (W2 is a positive integer including zero) is satisfied where the number of the second fuel rods arranged without being vertically and/or horizontally adjacent to each other in the horizontal section is W0, the number of the second fuel rods arranged vertically and/or horizontally adjacent to only one second fuel rod in the horizontal section is W1, and the number of the second fuel rods arranged vertically and/or horizontally adjacent to two second fuel rods in the horizontal section is W2, of the second fuel rods arranged on the outermost periphery.

The invention discloses an MOX fuel rod bundle assembling method and device. The method comprises the steps that S1, relative pose information between lower end plugs of MOX fuel rods and a grid plate is obtained; and S2, according to the relative pose information between the lower end plug of the MOX fuel rod and the grid plate, the pose of the lower end plug of the MOX fuel rod is adjusted to be consistent with the pose of the grid plate, so that the lower end plug is inserted into the grid plate. The invention further discloses a device for assembling the MOX fuel rod bundle. According to the MOX fuel rod assembling machine, automatic assembling of MOX fuel rods can be achieved, and the assembling safety and assembling efficiency of the MOX fuel rods are improved.

The invention relates to the technical field of nuclear-grade powder pellet sintering and particularly discloses a wet hydrogen sintering method of a MOX fuel pellet. The wet hydrogen sintering methodof the MOX fuel pellet comprises the following steps that firstly, feeding green bodies into a furnace; secondly, conducting gas replacement for flushing; thirdly, conducting wet hydrogen sintering;and fourthly opening the furnace. According to the wet hydrogen sintering method of the MOX fuel pellet, by controlling sintering temperature, the temperature keeping time, the sintering atmosphere and other key parameters in the sintering process, the specific sintering stages are optimized, the technical problems that the density of the pellet is uneven, the density is low, the O/M ratio is on the high side, and grains are under size are solved, and the wet hydrogen sintering method provides the corresponding technical support for volume production.