摘要:
Disclosed is a fuel rod auto-loading apparatus for a nuclear fuel assembly, which disposes fuel rods in a fuel rod case in a bundle to assemble the fuel rods into the nuclear fuel assembly. The fuel rod auto-loading apparatus includes a fuel rod storage unit having a plurality of stacked racks for fuel rods, a fuel rod loading unit raised/lowered to the racks and transferring the fuel rods, a feeding unit placing the fuel rods in rows and loading the fuel rods into the fuel rod case, a fuel rod unloading unit selectively unloading some of the fuel rods stored in the fuel rod storage unit and transferring the fuel rods to the feeding unit, a fuel rod assembly lifter which is disposed parallel to the feeding unit, and a controller controlling driving of the fuel rod loading unit, the feeding unit, and the fuel rod unloading unit.
摘要:
Disclosed herein are zirconium alloy compositions having a low hydrogen pick-up rate and high hydrogen embrittlement resistance. This zirconium alloy composition can be usefully used as a nuclear fuel components in a nuclear power plant because it has a very low hydrogen pick-up rate and high hydrogen embrittlement resistance under operation environments of nuclear power plant.
摘要:
A zirconium alloy is manufactured through melting; solution heat treatment at 1,000 to 1,050° C. (β) for 30 to 40 min and β-quenching using water; preheating at 630 to 650° C. for 20 to 30 min and hot rolling at a reduction ratio of 60 to 65%; primary intermediate vacuum annealing at 570 to 590° C. for 3 to 4 hr and primarily cold-rolled at a reduction ratio of 30 to 40%; secondary intermediate vacuum annealing at 560 to 580° C. for 2 to 3 hr and secondarily cold-rolled at a reduction ratio of 50 to 60%; tertiary intermediate vacuum annealing at 560 to 580° C. for 2 to 3 hr and tertiarily cold-rolled at a reduction ratio of 30 to 40%; and final vacuum annealing at 460 to 590° C. for 7 to 9 hr.
摘要:
Disclosed is a water-soluble coating composition, which is applied on the surface of fuel rods to prevent scratching of the surface of the fuel rods upon manufacturing a nuclear fuel assembly for light water reactors. This water-soluble coating composition facilitates the formation and removal of a coating film and the resulting coating film can exhibit strength and durability equivalent to those of an existing lacquer (nitrocellulose) coating film, and can thus be used as an alternative to lacquer, thereby easily removing the coating film and improving workplace safety, ultimately achieving improvements in the working environment and high workplace safety.
摘要:
A charging device of a welding fixture of spacer grid comprises a base frame; a conveyor for conveying a welding fixture horizontally over the base frame; and a gripper located over the base frame for gripping a welding fixture conveyed along the conveyor to charge a welding fixture into a welding chamber, wherein the gripper comprises a gripper body; and a gripping part installed horizontal to the end of the gripper body for gripping a welding fixture and capable of tilting in vertical direction to the gripper body in case more than a predetermined load is applied as a vertical load.
摘要:
A melting apparatus for melt-decontaminating radioactive metal waste includes a melting furnace, a high frequency generator, a ladle, a bogie, a cooling unit and a dust collector. In detail, the melting furnace includes a crucible into which the metal waste is input, and an induction coil which is wound around the crucible to melt the metal waste. The induction coil has a hollow hole in which cooling fluid flows. The high frequency generator applies high-frequency current to the induction coil. The ladle supplies molten metal, from which slag has been removed in the crucible, into molds. The bogie is disposed adjacent to the ladle and is provided with the molds, each of which forms an ingot using the molten metal supplied thereinto. The cooling unit cools the cooling fluid and circulates it along the induction coil. The dust collector filters out dust and purifies gas.
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 is a fuel rod auto-loading apparatus for a nuclear fuel assembly, which disposes fuel rods in a fuel rod case in a bundle to assemble the fuel rods into the nuclear fuel assembly. The fuel rod auto-loading apparatus includes a fuel rod storage unit having a plurality of stacked racks for fuel rods, a fuel rod loading unit raised/lowered to the racks and transferring the fuel rods, a feeding unit placing the fuel rods in rows and loading the fuel rods into the fuel rod case, a fuel rod unloading unit selectively unloading some of the fuel rods stored in the fuel rod storage unit and transferring the fuel rods to the feeding unit, a fuel rod assembly lifter which is disposed parallel to the feeding unit, and a controller controlling driving of the fuel rod loading unit, the feeding unit, and the fuel rod unloading unit.
摘要:
Disclosed is an automatic welding apparatus for an end plug of a nuclear fuel rod, which is used to perform resistance welding on a cladding tube and the end plug in a welding chamber. The automatic welding apparatus includes a welding chamber configured to perform resistance welding on an end plug and a cladding tube, a cladding tube transfer unit that has a cladding tube clamp fixedly clamping the cladding tube and a first servo motor for driving the cladding tube clamp in a horizontal direction and that horizontally transfers the cladding tube to the welding chamber, end plug welding electrodes gripping the end plug fed from an end plug feeder, an end plug transfer driver for driving the end plug welding electrodes toward the welding chamber in a forward/backward direction, and a position control module for controlling driving of the first servo motor and the end plug transfer driver.
摘要:
Disclosed herein is a melting apparatus for melt-decontaminating radioactive metal waste. The melting apparatus includes a melting furnace, a high frequency generator, a ladle, a bogie, a cooling unit and a dust collector. The melting furnace includes a crucible into which the metal waste is input, and an induction coil which is wound around the crucible to melt the metal waste. The induction coil has a hollow hole in which cooling fluid flows. The high frequency generator applies high-frequency current to the induction coil. The ladle supplies molten metal, from which slag has been removed in the crucible, into molds. The bogie is disposed adjacent to the ladle and is provided with the molds, each of which forms an ingot using the molten metal supplied thereinto. The cooling unit cools the cooling fluid and circulates it along the induction coil. The dust collector filters out dust and purifies gas.