摘要:
Provided herein is a control method for volume fraction of multistructural isotropic fuel particles in a fully ceramic microencapsulated nuclear fuel including: preparing a mixture of silicon carbide, sintering additives, and organic binders, producing a coating body by coating multistructural isotropic fuel particles by using the prepared mixture, forming the coating body, and performing pressureless sintering on the formed coating body, wherein volume fraction of multistructural isotropic nuclear fuel particles may be controlled by controlling the coating layer thickness on multistructural isotropic nuclear fuel particles, wherein the coating layer was configured with a mixture of silicon carbide, sintering additives, and organic binders. As described above, stability and tolerance against nuclear fuel related accidents may be significantly enhanced, and advantageous effects of enabling a pressureless sintering procedure to be performed while maximizing volume fraction of the multistructural isotropic fuel particles may be expected.
摘要:
The present invention relates to a method for preparing a fully ceramic capsulated nuclear fuel material containing three-layer-structured isotropic nuclear fuel particles coated with a ceramic having a composition which has a higher shrinkage than a matrix in order to prevent cracking of ceramic nuclear fuel, wherein the three-layer-structured nuclear fuel particles before coating is included in the range of between 5 and 40 fractions by volume based on after sintering. More specifically, the present invention provides a composition for preparing a fully ceramic capsulated nuclear fuel containing three-layer-structured isotropic particles coated with the substance which includes, as a main ingredient, a silicon carbine derived from a precursor of the silicon carbide wherein a condition of ΔLc>ΔLm at normal pressure sintering is created, where the sintering shrinkage of the coating layer of the three-layer-structured isotropic nuclear fuel particles is ΔLc and the sintering shrinkage of the silicon carbide matrix is ΔLm; material produced therefrom; and a method for manufacturing the material. The residual porosity of the fully ceramic capsulated nuclear fuel material is 4% or less.
摘要:
Provided is a nuclear fuel pellet having excellent compression resistance and a reduced missing pellet surface, the pellet being a cylindrical shape and including, on each of a top surface and a bottom surface thereof: a dish configured as a spherical groove shape having a predetermined curved surface at a center; a land configured as a horizontal annular shape along a rim of the dish; and a chamfer configured as a shape in which a corner is chamfered at a predetermined angle along a rim of the land, wherein the chamfer includes: a primary chamfer adjacent to the rim of the land; and a secondary chamfer configured as a shape additionally chamfered along a rim of the primary chamfer.
摘要:
Provided is mobile equipment for measuring structural deformation of a nuclear fuel assembly, the mobile equipment including: a container; a power means and a loading table disposed inside the container; a pedestal disposed on one side of the loading table of the container, the pedestal being provided with a hinge means and a fixing means configured to fix the nuclear fuel assembly upright; a column seated on the loading table and provided at one end part thereof with a rotating shaft detachably installed to the hinge means, and configured to be erected upright on the fixing means of the pedestal by power of the power means; and a scanner configured to move upward and downward in a longitudinal direction of the column and to measure the structural deformation of the nuclear fuel assembly.
摘要:
A combination of a top nozzle and a guide thimble of a nuclear fuel assembly and, more particularly, a structure for joining an inner-extension tube, the top nozzle and the guide thimble. When an inner-extension tube head, which is provided as a means for facilitating removal of the top nozzle of the nuclear fuel assembly from the guide thimble, is removed from an inner-extension tube body to separate the top nozzle from the nuclear fuel assembly, the inner-extension tube body is prevented from undesirably rotating, so that the guide thimble and the inner-extension tube body can maintain the joined state.
摘要:
Disclosed is a method of predicting, calculating, or analyzing the sintered density of uranium oxide (UOx) before uranium oxide is added in the pelletizing process during a process of manufacturing nuclear fuel, the method including measuring the chromaticity of ammonium diuranate using a spectrophotometer. The present invention provides a simple and highly reliable method of predicting the sintered density of uranium oxide (UOx), which overcomes the problem with a conventional technology where the sintered density of uranium oxide (UOx) can be analyzed only in a pellet state and a subsequent treatment process needs to be performed according to the analysis result.
摘要:
A fuel pellet visual inspection device for manufacturing a nuclear fuel rod improves convenience and workability of visual inspection of a plurality of pellets by simultaneously turning over the pellet. The fuel pellet visual inspection device for manufacturing a nuclear fuel rod includes: a rotary shaft; a pair of seats hinged to the hinge shaft, arranged at both sides from the rotary shaft, and seated with a tray thereon; and a dust-collecting unit disposed under the pair of seats and collecting dust scattered from pellets.
摘要:
A gap control device for a Pilger die assembly of cold Pilger mills. The gap control device can independently control the height of a pair of bearing blocks which axially support an upper die. A lower plate has first and second receiving holes which respectively correspond to the upper portions of a pair of bearing blocks. First and second wedge plates are fitted into the receiving holes, and respectively have inclined surfaces on the upper portions thereof. First and second adjustment blocks respectively have inclined guide surfaces to be in surface contact with the inclined surfaces of the wedge plates, and are movable horizontally with respect to the lower plate. An upper plate is assembled to the upper portion of the lower plate to cover the adjustment blocks. First and second adjustment bolts allow the first and second adjustment blocks to be respectively manipulated in a horizontal direction.
摘要:
Disclosed herein is a spacer grid for a nuclear fuel assembly which is formed from grid strips of an improved structure, thus reducing flow-induced high-frequency vibration. The spacer grid has dimples or grid springs for supporting fuel rods and is formed from a plurality of grid strips assembled in a lattice shape to form lattice cells. Each of the grid strips has at least one slot formed in a planar portion of the grid strip separately from the dimple or grid spring. Therefore, characteristics of the vibration of the spacer grid can be set in a variety of different manners so that flow-induced high-frequency vibration can be reduced.
摘要:
Disclosed is a plasma welding apparatus for a guide thimble and guide thimble end plug of a nuclear fuel assembly, which includes: a welding chamber (100) includes an end-plug inserting part (110) into which the end plug (10) is inserted, a guide-thimble inserting part (120) which is provided on the same axis as the end-plug inserting part (110) and into which the guide thimble (20) is inserted and fixed, a torch assembling part (130) to which a plasma welding torch (131) is assembled so as to make a right angle with the end-plug inserting part (110) and the guide-thimble inserting part (120), and argon inflow and outflow ports (141, 142) through which argon is supplied or discharged; an end-plug transfer unit (210) supplying the end plug (10) to the end-plug inserting part (110); and an guide-thimble transfer unit (220) transferring the guide thimble (20) to the guide-thimble inserting part (120).