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 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 method of detecting a cancer progression observation index gene group, comprising: a) preparing a plurality of AKR/J mice in which an oncogene is inserted into a thymocyte; b) dividing the AKR/J mice into three groups, raising the first group of the AKR/J mice after high-dose ionizing radiation of 0.8 Gy/min, raising the second group of the AKR/J mice after low-dose ionizing radiation of 0.

Abstract: Disclosed is a uranium dioxide nuclear fuel pellet, which includes metallic microcell partitions having a high protection capacity for fission products and a high thermal conductivity simultaneously. These metal microcell partitions are arranged in the nuclear fuel pellet to trap fission products. Further disclosed is a method of making the uranium dioxide nuclear fuel pellet. The method includes providing a mixture of uranium dioxide powder and additive powder of Cr-containing compound or Mo-containing compound; compressing the powder mixture to form a green pellet; and then sintering the green pellet under reducing gas environment to form the metallic microcell partitions.

Abstract: A steel plate structure and a steel plate concrete wall are disclosed. A steel plate structure, which includes: a pair of steel plates, which are separated to provide a predetermined space; a structural member, which is positioned in the predetermined space, and which is structurally rigidly joined to one side of the steel plate in the direction of gravity; and a strut, which maintains a separation distance between the pair of steel plates, can be utilized to reduce the overall thickness of a steel plate concrete wall for efficient use of space, and to reduce the thickness of the steel plates for better welding properties and larger unit module sizes. Also, the axial forces or lateral forces applied on the steel plate concrete wall may be effectively resisted.

Abstract: The present disclosure relates to a method for measuring electrical conductivity and a system for measuring electrical conductivity using the same. The method includes obtaining a cell constant of a conductance cell using a conductivity standard solution, pouring a solution desired to be measured in the conductance cell, and applying predetermined direct current (DC) voltages to electrodes, disposed in the conductance cell, in a manner of changing the predetermined DC voltages in stages at each preset time (t), obtaining resistance of the solution, as a slope, from a linear relationship between the voltage and a peak current, measured for each voltage, and calculating electrical conductivity of the solution using the cell constant and the resistance of the solution.

Abstract: Disclosed herein is a high Cr Ferritic/Martensitic steel comprising 0.04 to 0.13% by weight of carbon, 0.03 to 0.07% by weight of silicon, 0.40 to 0.50% by weight of manganese, 0.40 to 0.50% by weight of nickel, 8.5 to 9.5% by weight of chromium, 0.45 to 0.55% by weight of molybdenum, 0.10 to 0.25% by weight of vanadium, 0.02 to 0.10% by weight of tantalum, 0.21 to 0.25% by weight of niobium, 1.5 to 3.0% by weight of tungsten, 0.015 to 0.025% by weight of nitrogen, 0.01 to 0.02% by weight of boron and iron balance. By regulating the contents of alloying elements such as nitrogen, born, the high Cr Ferritic/Martensitic steel with superior tensile strength and creep resistance is provided, and can be effectively used as an in-core component material for sodium-cooled fast reactor (SFR).

Abstract: A nuclear fuel rod for fast reactors includes a metallic fuel slug coated with a protective coating layer. In embodiments, a nuclear fuel rod for fast reactors includes a uranium and zirconium fuel slug having a single protective coating which is an oxide layer having a thickness in the range of 0.5 ?m to 100 ?m, and the protective coating layer may be configured to (i) prevent interdiffusion between the fuel slug and a cladding tube during fast reactor operation, and (ii) prevent a cladding tube from thinning during fission operation in a fast reactor.

Abstract: The present invention relates to a passive nitrogen injecting device for a nuclear reactor coolant pump, the device comprising: a nitrogen supply unit for supplying nitrogen; a pressure control valve for controlling the supply of nitrogen from the nitrogen supply unit according to pressure; an accumulator for filling the nitrogen supplied through the pressure control valve at a set pressure, and supplying the filled nitrogen in the event that an accident involving coolant loss occurs; and an isolation valve for controlling the supply of the nitrogen from the accumulator into a seal housing of a nuclear reactor coolant pump. The present invention uses an accumulator so as to be able to supply nitrogen by using the pressure in the accumulator without the supply of external power in the event of an accident involving coolant loss, and therefore has the effect of being able to improve safety.

Abstract: Provided is a coil assembly having improved heat resistance for use in a control rod driver, in which the heat resistance of coils is improved to increase the lifespan thereof and the deterioration of the coils and the fall of a control rod are thus securely prevented from occurring due to continuous operations of the control rod driver during an automatic load follow operation, thereby improving the safety and economic feasibility of a nuclear power plant, and a method for manufacturing the same.

Abstract: A method for fabricating porous UO2 sintered pellets to be fed into the electrolytic reduction process for the purpose of metallic nuclear fuel recovery is provided, which includes forming a powder containing U3O8 by oxidizing spent nuclear fuel containing uranium dioxide (UO2) (step 1), fabricating green pellets by compacting the powder formed in step 1 (step 2), fabricating UO2+x sintered pellets by sintering the porous U3O8 green pellets fabricated in step 2 at 1200 to 1600° C., in an atmospheric gas (step 3), and forming UO2 sintered pellets by cooling the UO2+x sintered pellets to room temperature, and reduction the same at 1000 to 1400° C., in a reducing atmosphere (step 4).

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: 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: This invention relates to the vitrification of radioactive waste products. According to this invention, a glass composition that is suitable for mixed waste products, which include flammable waste products, such as gloves, working clothes, plastic waste, and rubber, and low-level radioactive waste products, and a method of vitrifying the mixed waste products using the same are provided to significantly reduce the volume of radioactive waste products and to vitrify the mixed waste products using the glass composition, which is suitable for vitrifying the mixed waste products, thereby maximally delaying or completely preventing the leakage of radioactive materials from a glass solidified body.

Abstract: A zirconium alloy for use in nuclear fuel assemblies is provided, which provides increased resistance against oxidation and corrosion and also improved bonding with parent material, because pure metallic material such as silicon (Si) or chromium (Cr) is evenly coated on the surface of the parent material by plasma spraying. Because the plasma spray coating used to coat the pure metallic material on the zirconium alloy does not require vacuum equipment and also is not limited due to the shape of the coated product, this is particularly useful when evenly treating the surface of the component such as 4 m-long tube or spacer grip arrangement which is very complicated in shape. Furthermore, because the coated zirconium alloy confers excellent resistance to oxidation and corrosion under emergency such as accident as well as normal service condition, both the economic and safety aspects of nuclear fuel are improved.

Abstract: An oxide dispersion strengthening (ODS) method of a metallic material using a laser is provided, which includes melting a surface of a metallic matrix placed on a movable stage by irradiating a laser onto the surface (step 1), supplying an oxide dispersion strengthening (ODS) powder at a site of the matrix surface which is melt at step 1 (step 2), and cooling the matrix in which the ODS powder is supplied at step 2 (step 3). Because oxide particles are directly supplied into previously-made sheet or tube matrix, fabrication process is simplified, fabrication cost is reduced, and end product is fabricated efficiently.

Abstract: Provided are a tube sheet of a steam generator installed to support a tube of the steam generator, and a manufacturing method thereof, particularly, a tube sheet of a steam generator having an anticorrosive layer and a manufacturing method thereof.

Abstract: A monitoring method of metal ions or oxygen ions applicable to a high concentration non-aqueous electrolyte includes: applying a potential in a non-aqueous electrolyte to obtain current information with respect to the potential; varying the potential applied in the non-aqueous electrolyte containing metal ion concentration or oxygen ion concentration such that the metal ion concentration or the oxygen ion concentration is maintained in spite of the potential being applied; detecting a linear relationship among the concentration, the current, and passed charges in the non-aqueous electrolyte by repeatedly performing the obtaining step and the varying step, while changing the concentration; and calculating metal ion concentration or oxygen ion concentration of the non-aqueous electrolyte in pyroprocessing of the non-aqueous electrolyte by using the linear relationship.

Abstract: A cold crucible induction melter includes an induction coil and a melting furnace. The induction coil serves as a water cooled segment to directly transmit an induced current to a molten material in the cold crucible induction melter (CCIM), improving energy efficiency. Simultaneously, the structure of the CCIM is simplified and enables a smooth discharge even when the molten material consists of a ceramic or a metal material with a high melting point. The cold crucible induction melter heats and melts waste using an induced current which is generated in a water cooled segment by a high frequency current that is applied to the induction coil. The water cooled segment and the induction coil are disposed in a vertical direction so that the induced current that is generated by the induction coil is directly transmitted to the molten material.

Abstract: A cold crucible induction melter includes a wall formed of a plurality of metal sectors insulated by an insulator. Each metal sector includes an outer curved portion which forms an outer surface of the wall and is convex outward relative to the wall, an inner planar portion which forms an inner surface of the wall, and two side planar portions which connect the inner curved portion to the outer planar portion. The metal sector further includes a cooling passage longitudinally formed inside the metal sector, and an insulation layer covering the inner curved portion and the two side planar portions.