Abstract: A magnetic alignment device includes a first magnet part and a second magnet part, a thickness measuring part, and a control part. The first and second magnet parts accommodate an electrode sheet therebetween and the thickness measuring part measures a thickness of a negative electrode slurry disposed on the electrode sheet. The control part adjusts the separation distance of the first and second magnet parts. The magnetic alignment device measures the thickness of the negative electrode slurry applied on the negative electrode current collector in real time and controls the intensity of the magnetic field by adjusting the separation distance of the magnet part according to the measured negative electrode slurry thickness, and has an advantage of uniformly high alignment degree of the crystal faces of the carbon-based negative electrode active material contained in prepared negative electrode active layer.

Abstract: Disclosed is a blood-compatible polymer represented by Formula 1. A polymer obtained by grafting a fluorinated methacrylate onto a polyvinylidene fluoride copolymer and provided in one aspect of the present invention is a polymer with blood compatibility, and may provide a blood-compatible material with hydrophobicity. In addition, it is possible to provide a material with controlled contact angle and surface energy properties by controlling the hydrogen fluoride length of the fluorinated methacrylate monomer for modification. Furthermore, it is possible to provide coating with controlled surface properties and blood compatibility through a simple process. Furthermore, it is possible to provide a freestanding polymer film with blood compatibility.

Abstract: A magnetic alignment device includes a first magnet part and a second magnet part, a loading amount measuring part, and a control part. The first and second magnet parts accommodate an electrode sheet therebetween and the loading amount measuring part measures a loading amount of a negative electrode slurry disposed on the electrode sheet. The control part adjusts the separation distance of the first and second magnet parts, The magnetic alignment device measures the loading amount of the negative electrode slurry applied on the negative electrode collector in real time and controls the intensity of the magnetic field by adjusting the separation distance of the magnet part according to the measured negative electrode slurry loading amount. A method using the same is also provided.

Abstract: A magnetic alignment device for negative electrode and method for manufacturing negative electrode using the same. The magnetic alignment device can measure the loading amount of the negative electrode slurry applied on the negative electrode collector in real time and can easily control the intensity of the magnetic field by adjusting the separation distance of the magnet portion according to the measured negative electrode slurry loading amount, and has an advantage of uniformly high alignment degree of the crystal faces of the carbon-based negative electrode active material contained in prepared negative electrode active layer.

Abstract: A heat treatment apparatus includes a furnace body, a roller inside the furnace body, a heater inside the furnace body, an upper and lower discharge pipes on the furnace body, and a lower supply pipe on the lower part of the furnace body. The furnace body includes areas having the upper and lower discharge pipes, the areas including a first area to an Nth area disposed sequentially along a second direction being a transport direction of each of the materials, a length of the first area in the second direction is shorter than lengths of the second area to the Nth area in the second direction, and in each of the first area to the Nth area, the upper discharge pipe and the lower supply pipe are not arranged in a straight line in a third direction being a height direction to be misaligned from each other.

Abstract: 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.

Abstract: 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.

Abstract: A joint structure between 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.

Abstract: A joint structure between 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.

Abstract: Disclosed herein is a joint structure between a top nozzle and a guide thimble. The joint structure includes an outer guide post, an inner-extension tube head, an inner-extension tube body, a wedge and the guide thimble. The outer guide post is provided with an external thread formed on a lower end thereof. The inner-extension tube head includes an annular retaining part formed on an upper end thereof. An internal thread is formed on a medial portion of the inner-extension tube head. An external thread is formed on each of upper and lower ends of the inner-extension tube body. A stop protrusion is provided under a lower end of the wedge. The wedge is welded to the inner-extension tube body after the top nozzle has been joined with the guide thimble. A stop protrusion receiving depression is formed in the guide thimble.

Abstract: Disclosed herein is a joint structure between a top nozzle and a guide thimble. The joint structure includes an outer guide post, an inner-extension tube head, an inner-extension tube body, a wedge and the guide thimble. The outer guide post is provided with an external thread formed on a lower end thereof. The inner-extension tube head includes an annular retaining part formed on an upper end thereof. An internal thread is formed on a medial portion of the inner-extension tube head. An external thread is formed on each of upper and lower ends of the inner-extension tube body. A stop protrusion is provided under a lower end of the wedge. The wedge is welded to the inner-extension tube body after the top nozzle has been joined with the guide thimble. A stop protrusion receiving depression is formed in the guide thimble.

Abstract: The present invention relates to a top nozzle for a nuclear fuel assembly that has a two-stage elastic section such that a pushing force against the axial movement of the nuclear fuel assembly under normal conditions is optimized and at the same time a suppressing force against a drastic uplifting force of the nuclear fuel assembly under transient conditions is strengthened, and that lowers the elastic coefficients of the springs operating under normal conditions more than those of existing coil springs, thereby providing an optimal pushing force against the nuclear fuel assembly.

Abstract: The present invention relates to a fuel rod of a nuclear fuel assembly having a vase-like compression spring adapted to increase the internal volume thereof wherein when the vase-like compression spring is inserted into a cladding tube, it has a relatively smaller volume occupied inside the fuel rod when compared with the existing coil type compression spring, such that the vase-like compression spring can ensure a sufficient space portion receiving the fission gases generated during the operation of the fuel rod, thereby increasing the burn-up performance of the fuel rod and the mechanical integrity thereof.

Abstract: The present invention relates to an anti-fretting wear spacer grid having a plurality of canoe-shaped springs formed thereon, wherein each of the canoe-shaped springs includes: a fuel rod-contacting part having a flat surface having a predetermined longitudinal length so as to have linear contact with the fuel rod; a curved face-connecting part formed on the upper and lower portions of the fuel rod-contacting part; a leg-connecting part formed on the end portion of the curved face-connecting part; and legs each being formed of a plate shape having a predetermined length and connecting the both sides of the leg-connecting part with one unit grid cell surface.

Abstract: The present invention relates to a top nozzle having on-off type of hold-down springs for a nuclear fuel assembly that has a two-stage elastic section such that a pushing force against the axial movement of the nuclear fuel assembly under normal conditions is optimized and at the same time a suppressing force against a drastic uplifting force of the nuclear fuel assembly under transient conditions is strengthened, and that lowers the elastic coefficients of the springs operating under normal conditions more than those of existing coil springs, thereby providing an optimal pushing force against the nuclear fuel assembly.

Abstract: The present invention relates to an anti-fretting wear spacer grid having a plurality of canoe-shaped springs formed thereon, wherein each of the canoe-shaped springs includes: a fuel rod-contacting part having a flat surface having a predetermined longitudinal length so as to have linear contact with the fuel rod; a curved face-connecting part formed on the upper and lower portions of the fuel rod-contacting part; a leg-connecting part formed on the end portion of the curved face-connecting part; and legs each being formed of a plate shape having a predetermined length and connecting the both sides of the leg-connecting part with one unit grid cell surface.

Abstract: Disclosed herein is a joining structure between a top nozzle and guide thimbles in a nuclear fuel assembly, which can prevent a rotation of inner insertion tube bodies when the top nozzle is separated from the nuclear fuel assembly and promote convenience in assembling and disassembling the top nozzle and the guide thimbles.

Abstract: The present invention relates to a fuel rod of a nuclear fuel assembly having a vase-like compression spring adapted to increase the internal volume thereof wherein when the vase-like compression spring is inserted into a cladding tube, it has a relatively smaller volume occupied inside the fuel rod when compared with the existing coil type compression spring, such that the vase-like compression spring can ensure a sufficient space portion receiving the fission gases generated during the operation of the fuel rod, thereby increasing the burn-up performance of the fuel rod and the mechanical integrity thereof.