Abstract: The present disclosure relates to an automatic inspection apparatus for generator turbines and a system using the same. The automatic inspection apparatus adjusts the height of an arm via a lifter, adjusts a rotating angle relative to an inspection object via a rotator, and adjusts forward or backward movement of a probe relative to the inspection object via an expansion/contraction unit while moving the arm having the probe on a rail in accordance with positions of a turbine to be inspected. Furthermore, a compression unit may be used to control contact pressure of the probe to the inspection object at a desired level to allow the probe to closely contact the inspection object, thereby preventing disturbance due to vibration of the probe. In addition, the automatic inspection apparatus has a simple and lightweight configuration so as to be easily installed or removed in a work site.

Abstract: A dual-cooled fuel rod's spacer grid with upper and lower dimples, including a blocking area of a flow passage that coolant flows through is reduced and dual-cooled fuel rods are supported, and reduces a turbulent flow of the coolant as well as vibrations of the dual-cooled fuel rods, thereby lessening fretting damage done to the rods. The spacer grid includes a plurality of unit grid straps, each of which includes a body disposed in a vertical direction, an upper dimple protruding from an upper portion of the body, and a lower dimple spaced apart from the upper dimple in a downward direction and protruding from a lower portion of the body. The unit grid straps form a grid structure that have inner grid holes into which the dual-cooled fuel rods are held, and the held dual-cooled fuel rods are each supported in four directions by the upper and lower dimples.

Abstract: Disclosed are a zirconium alloy for a nuclear fuel cladding having a good corrosion resistance by reducing an amount of alloying elements and a method of preparing a zirconium alloy nuclear fuel cladding using thereof. The zirconium alloy includes 0.2 to 0.5 wt % of niobium (Nb); 0.2 to 0.6 wt % of iron (Fe); 0.3 to 0.5 wt % of chromium (Cr); 0.1 to 0.15 wt % of oxygen (O); 0.008 to 0.012 wt % of silicon (Si) and a remaining amount of zirconium (Zr). The total amount of the niobium, the iron and the chromium is 1.1 to 1.2 wt %. A good oxidation resistance of the nuclear fuel cladding may be confirmed under accident conditions as well as normal operating conditions of a reactor, thereby improving economic feasibility and safety.

Abstract: Provided is a hydraulic test device for head loss of a strainer and a test method thereof, wherein the hydraulic test device comprises a circulation pipe; an inflow container; a container; a debris interceptor; sensors; a circulation pump; a flow meter; a circulation heating heater; and a data acquisition part which stores data sensed by each sensor, flow rate data.

Abstract: Disclosed are a zirconium alloy for a nuclear fuel cladding having a good oxidation resistance in a severe reactor operation condition and a method of preparing zirconium alloy nuclear fuel claddings by using thereof. The zirconium alloy includes 1.8 to 2.0 wt % of niobium (Nb); at least one element selected from iron (Fe), chromium (Cr) and copper (Cu); 0.1 to 0.15 wt % of oxygen (O); 0.008 to 0.012 wt % of silicon (Si) and a remaining amount of zirconium (Zr). The amount of Fe is 0.1 to 0.4 wt %, the amount of Cr is 0.05 to 0.2 wt %, and the amount of Cu is 0.03 to 0.2 wt %. A good oxidation resistance of the nuclear fuel cladding may be confirmed under a severe reactor operation condition at an accident condition as well as a normal operating condition of a reactor, thereby improving economic efficiency and safety.

Abstract: An apparatus and method for monitoring a flow of liquid in a pipe are provided. The apparatus may include a temperature sensor attached to a pipe of a heat exchanger system to measure a temperature of the pipe, and a controller to determine whether a liquid is present in the pipe, based on a change in the measured temperature.

Abstract: Disclosed are a zirconium alloy for a nuclear fuel cladding having a good oxidation resistance in reactor accident conditions, a zirconium alloy nuclear fuel cladding prepared by using thereof and a method of preparing the same. The zirconium alloy includes 1.0 to 1.2 wt % of niobium (Nb); at least one element selected from tin (Sn), iron (Fe) and chromium (Cr); 0.02 to 0.1 wt % of copper (Cu); 0.1 to 0.15 wt % of oxygen (O); 0.008 to 0.012 wt % of silicon (Si) and a remaining amount of zirconium (Zr). The amount of Sn is 0.1 to 0.3 wt %, the amount of Fe is 0.3 to 0.8 wt %, and the amount of Cr is 0.1 to 0.3 wt %. A good oxidation resistance of the nuclear fuel cladding may be confirmed under accident conditions as well as normal operating conditions of a reactor, thereby improving economic efficiency and safety.

Abstract: The present invention relates to a method and apparatus for solidifying radioactive waste accompanying chlorine recycling or radioactive iodine removal. The present invention provide a method and apparatus for treating radioactive waste composed of volatile metal halide with high corrosiveness at a high temperature through a solidifying system including crushing, mixing/dehalogenating and sintering. In the inventive method and apparatus for solidifying radioactive waste, a dechlorination process by using a dehalogenation material is performed on highly corrosive metal salt under an oxidizing atmosphere by using a method of controlling a temperature on the surface of a reactor, and solidification is carried out by removing radioactive iodine while reusing chlorine contained in an exhaust gas. Accordingly, the generated amount of total waste can be reduced, and therefore the inventive method and apparatus can be usefully used in preparing a solidified body with high durability.

Abstract: Provided is a diagnostic method and system capable of applying tomography to industrial long cylindrical process systems, such as a pipe line, which are difficult to diagnose using existing medical or industrial computed tomography (CT) scanners. Existing industrial X-ray CT scanners cannot be used for such a pipe that is attached to the process system and thus cannot be placed on the turntable, and existing image diagnostic apparatuses of a fan beam type, a collimated beam type, etc. having a stereotyped structure are next to impossible to move and use for undetachable process systems and their peripheral devices. To solve these problems, there is provided a gamma-ray tomography scanning system that is capable of being directly attached to a pipe in operation and measuring a cross section of the pipe.

Abstract: A method for detecting genes sensitive to low-level ionizing radiation and genes detected by the method. More specifically, genes sensitive to low-level ionizing radiation, discovered in a carcinogenic entity and verified in a normal entity are detected by subjecting a cancerous AKR/J mouse and a normal ICR mouse to low-level radiation. Thymus is collected therefrom, and glycometabolism-related genes are classified via microarray processing of the thymus. The genes are amplified and the levels of gene expression are measured. Thus, a gene having a specific reaction to radiation can be accurately detected by preventing the interference of confounding variables.

Abstract: A radiation measuring system includes a whole-body counter having upper and lower radiation detectors that are located in front of a measurement space, which has an inlet passage and is located in a housing, and that detects respective internal radiations of a measurement target and first and second internal radiations of a body region corresponding to one of a thyroid gland, a lung, a whole body, or a hypogastrium, and a processor controlling determination of an internal radioactive contamination location of the measurement target, based on a ratio of the first and second internal radiations, applying the optimal measurement mode corresponding to the ratio of the first and second internal radiations, and detecting the first and second internal radiations of a body region corresponding to the internal radioactive contamination location.

Abstract: Provided is a vitrification process method of aluminum and filter radioactive wastes to produce high quality of glass solidification fit for legislations and rules as vitrification final product, comprising developing frit composition needed in vitrifying the aluminum and filter radioactive wastes, suitably mixing the aluminum and filter radioactive wastes with the frit and producing glass solidification having composition range of oxides of aluminum and filter radioactive wastes to maintain lower than 100 poise viscosity which is operating parameter of a melting furnace. The vitrification process method of aluminum and filter radioactive wastes comprise mixing the aluminum and filter radioactive wastes with the frit in an induction heating low temperature melting furnace and meting it at the temperature of 1,100˜1,200° C. to produce glass solidification.

Abstract: A waste liquid treatment apparatus with enhanced treatment capacity for a pre-treatment facility of a liquid radwaste treatment system for a nuclear power plant. The waste liquid treatment apparatus includes: a water tank into which a waste liquid is introduced and from which filtered permeated water is discharged; a waste liquid introduction section through which waste liquid is introduced into the water tank; submerged membranes annularly disposed and spaced apart from each other for filtering foreign substances from the waste liquid; a permeated water suctioning section suctioning the filtered water of the waste liquid and discharging the filtered water outside the water tank; an air supplying section supplying compressed air to the submerged membranes to remove foreign substances; and a porous support plate supporting the submerged membranes.

Abstract: The present invention is to solve the problems described above and to provide the plasma torch nozzle of graphite material coupled to the front electrode of the plasma torch by bolts. To achieve the object of the invention, the plasma torch nozzle according to this invention is characterized by that the torch nozzle is fixedly coupled to the front electrode of the plasma torch by one or more bolts.

Abstract: A tapping device and method using induction heat for melt comprises melting furnace made of steel; heating unit disposed in the upper part in the melting furnace and made of graphite material; induction coil wound around the heating unit; insulator disposed adjacent to the bottom surface of the lower part of the melting furnace; supporter disposed outside the insulator; and firebricks disposed on the bottom surface of melting furnace and outside the supporter.

Abstract: UO2 nuclear fuel pellets are fabricated by adding additive powder comprising Mn compound and Al compound into UO2 powder.

Abstract: A method of preparing a simple ceramic ingot of a spent filter having radioactive cesium trapped therein, and a ceramic ingot of a spent filter having improved properties such as leach resistance, thermal stability, and cesium content are provided. The method includes grinding and mixing a spent filter having cesium trapped therein, adding a solidifying agent, and sintering the spent filter. The method of preparing a ceramic ingot of a spent filter can be useful in preparing the ceramic ingot of the spent filter from only the spent filter by means of simple grinding and sintering, and in preparing the ceramic ingot of the spent filter by adding a small amount of a solidifying agent. The ceramic ingot of the spent filter has a high density and improved thermal stability, and shows improved leach resistance since a leach rate of a radioactive material is remarkably low. Therefore, the spent filter having radioactive cesium trapped therein can be effectively used to prepare a stable ceramic ingot.

Abstract: An apparatus and method for the granulation of radioactive waste in which a preprocessing method for the vitrification of radioactive waste is simplified to conform to onsite conditions of a nuclear power plant, additives are improved, and pellets suitable for vitrification are manufactured. The apparatus for the granulation of radioactive waste includes: a body frame having an inlet and an outlet; a hopper supplying the radioactive waste to be transferred and fed through the inlet; a feeder transferring/supplying the radioactive waste supplied to a specific position and in a certain quantity; a stirrer pulverizing/mixing lumps of the radioactive waste supplied; an additive supply part supplying a lubricant to the radioactive waste fed into the stirrer; and a pellet press pressing the radioactive waste fed through the feeder into a pellet shape and discharging the pellet through the outlet.

Abstract: Disclosed herein is an apparatus for recovering residual salt from the reduced uranium metal. The apparatus comprising: an evaporating chamber accommodating mixed molten salt or a reduced uranium metal; a heating furnace surrounding the evaporating chamber to heat the mixed molten salt in the evaporating chamber; an insulator disposed over the evaporating chamber to block heat generated from the evaporating chamber, and including an evaporating pipe in a center thereof to move vapor generated from the evaporating chamber; a receiver disposed over the insulator to collect powder formed by condensing and solidifying vapor passing through the evaporating pipe; and a condenser disposed over the receiver to prevent the vapor passing through the evaporating pipe from leaking out of the apparatus.

Abstract: A dual-cooled nuclear fuel rod and a method of manufacturing the same are provided. The nuclear fuel rod includes an outer cladding tube having a circular cross section, an inner cladding tube having an outer diameter smaller than an inner diameter of the outer cladding tube, and a length longer than the outer cladding tube, and located in parallel in the outer cladding tube, a pellet charged in a space between the outer and inner cladding tubes and generating energy by nuclear fission, and first and second end plugs coupling opposite ends of the outer cladding tube to stepped outer joints formed on outer circumferences of first ends thereof and coupling opposite ends of the inner cladding tube to stepped inner joints formed on inner circumferences of the first ends thereof.