Abstract: The present invention provides a water-cooled flue gas collecting apparatus disposed in a flow path formed inside a wake treatment structure for cooling and discharging flue gas generated from a test propulsion system. The water-cooled flue gas collecting apparatus includes a gas guiding portion having a flue gas inlet at one end through which the flue gas enters, a gas pipe connected to the flue gas inlet at one end to pass through the other end of the gas guiding portion and form an extension at the other end, and a collecting portion connected to the other end of the gas pipe to collect the flue gas entering through the gas pipe from the flue gas inlet. According to the present invention, the apparatus may be used in rocket propulsion systems of various sizes and allows quantitative analyses.

Abstract: The present invention relates to a seawater flow control device for a uniform motion, and more particularly, to a seawater flow control device for a uniform motion, which controls a velocity of a propulsion system by adjusting a combustion reaction between seawater and a propellant by adjusting a seawater flow rate depending on the number of operating seawater discharge holes. According to the present invention, it is possible to control the velocity of the propulsion system by increasing the amount of seawater when the velocity of the propulsion system is low and decreasing the amount of seawater when the velocity of the propulsion system is high, thereby implementing a uniform motion of the propulsion system.

Abstract: The present invention provides a crucible for melting and casting a metal fuel, which includes a reaction preventing layer including: LaYO3; or ZrO2 containing a Y2O3 stabilizer at 5 to 10 wt %, and a method of melting and casting a metal fuel using the same.

Abstract: The present invention provides a crucible for melting and casting a metal fuel, which includes a reaction preventing layer including: LaYO3; or ZrO2 containing a Y2O3 stabilizer at 5 to 10 wt %, and a method of melting and casting a metal fuel using the same.

Abstract: The proposed technology relates to a thrust control apparatus of a propulsion system, and more particularly, to a thrust control apparatus of a solid propulsion system equipped with an aerospike pintle nozzle. The present invention is to simultaneously control the magnitude and direction of thrust by installing a pintle and a thrust vectoring unit at the rear end of a combustion tube of a solid propulsion system.

Abstract: Provided is a thrust control apparatus having a plug area variable spike pintle nozzle, in which an aerospike-shaped pintle can be used in a pintle nozzle for precise thrust control. The thrust control apparatus includes a combustion chamber, a motor housing, and an outer pintle nozzle. The motor housing has a driving motor within the combustion chamber. The outer pintle nozzle is moved in a lateral direction by the driving motor.

Abstract: The proposed technology relates to a thrust control apparatus of a propulsion system, and more particularly, to a thrust control apparatus of a solid propulsion system equipped with an aerospike pintle nozzle. The present invention is to simultaneously control the magnitude and direction of thrust by installing a pintle and a thrust vectoring unit at the rear end of a combustion tube of a solid propulsion system.

Abstract: Provided are a nuclear fuel rod for fast reactors that includes a metallic fuel slug coated with a protective coating layer and a fabrication method thereof. The nuclear fuel rod for fast reactors that includes a surface treated metallic fuel slug and a cladding tube according to the present invention has an excellent effect of stabilizing components of the metallic fuel slug and fission products or impurities, because the interdiffusion between the metallic fuel slug and the cladding tube does not occur. Also, since the uniform coating on the surface of the metallic fuel slug may be facilitated and fabrication costs may be significantly reduced in comparison to a typical technique of using a functional material for preventing the interdiffusion at an inner surface of the cladding tube, it may be suitable for fabricating the nuclear fuel rod for fast reactors.

Abstract: Provided are a nuclear fuel rod for fast reactors that includes a metallic fuel slug coated with a protective coating layer and a fabrication method thereof. The nuclear fuel rod for fast reactors that includes a surface treated metallic fuel slug and a cladding tube according to the present invention has an excellent effect of stabilizing components of the metallic fuel slug and fission products or impurities, because the interdiffusion between the metallic fuel slug and the cladding tube does not occur. Also, since the uniform coating on the surface of the metallic fuel slug may be facilitated and fabrication costs may be significantly reduced in comparison to a typical technique of using a functional material for preventing the interdiffusion at an inner surface of the cladding tube, it may be suitable for fabricating the nuclear fuel rod for fast reactors.

Abstract: Provided are a nuclear fuel rod for fast reactors that includes a metallic fuel slug coated with a protective coating layer and a fabrication method thereof. The nuclear fuel rod for fast reactors that includes a surface treated metallic fuel slug and a cladding tube according to the present invention has an excellent effect of stabilizing components of the metallic fuel slug and fission products or impurities, because the interdiffusion between the metallic fuel slug and the cladding tube does not occur. Also, since the uniform coating on the surface of the metallic fuel slug may be facilitated and fabrication costs may be significantly reduced in comparison to a typical technique of using a functional material for preventing the interdiffusion at an inner surface of the cladding tube, it may be suitable for fabricating the nuclear fuel rod for fast reactors.

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: Provided are a nuclear fuel rod for fast reactors that includes a metallic fuel slug coated with a protective coating layer and a fabrication method thereof. The nuclear fuel rod for fast reactors that includes a surface treated metallic fuel slug and a cladding tube according to the present invention has an excellent effect of stabilizing components of the metallic fuel slug and fission products or impurities, because the interdiffusion between the metallic fuel slug and the cladding tube does not occur. Also, since the uniform coating on the surface of the metallic fuel slug may be facilitated and fabrication costs may be significantly reduced in comparison to a typical technique of using a functional material for preventing the interdiffusion at an inner surface of the cladding tube, it may be suitable for fabricating the nuclear fuel rod for fast reactors.

Abstract: Disclosed herein are a nuclear fuel rod for fast reactors, which includes an oxide coating layer formed on the inner surface of a cladding, and a manufacturing method thereof. The nuclear fuel rod for fast reactors, which includes the oxide coating layer formed on the inner surface of the cladding, can increase the maximum permissible burnup and maximum permissible temperature of the metallic fuel slug for fast reactors so as to prolong the its lifecycle in the fast reactors, thus increasing economic efficiency. Also, the fuel rod is manufactured in a simpler manner compared to the existing method, in which a metal liner is formed, and the disclosed method enables the cladding of the fuel rod to be manufactured in an easy and cost-effective way.

Abstract: Disclosed herein are a nuclear fuel rod for fast reactors, which includes an oxide coating layer formed on the inner surface of a cladding, and a manufacturing method thereof. The nuclear fuel rod for fast reactors, which includes the oxide coating layer formed on the inner surface of the cladding, can increase the maximum permissible burnup and maximum permissible temperature of the metallic fuel slug for fast reactors so as to prolong the its lifecycle in the fast reactors, thus increasing economic efficiency. Also, the fuel rod is manufactured in a simpler manner compared to the existing method, in which a metal liner is formed, and the disclosed method enables the cladding of the fuel rod to be manufactured in an easy and cost-effective way.

Abstract: The present invention relates to a multi-core fuel rod for research reactor and, more particularly, to a multi-core fuel rod for research reactor in which monolithic fuel cores made of uranium-molybdenum alloy are disposed in an aluminum matrix in a multi-core form. The multi-core fuel rod in accordance with the present invention provides a minimized contact surface area between nuclear fuel and aluminum, and reduces the formation of pores and swelling by restraining formation of reaction layer to avoid excessive reaction between the fuel and aluminum. Therefore, improved stability of nuclear fuel can be obtained by minimizing temperature rise as well as achieving high density and thermal conductivity of the fuel.

Abstract: Disclosed are a method and an apparatus for producing a uranium foil with fine crystalline granules by forming the foil by the gravitational dropping of molten uranium or uranium alloy and rapidly cooling the foil by the contact with cooling rolls, and a foil produced thereby. In accordance with the present invention, a high-purity and high-quality uranium foil with an isotropic structure and fine crystalline granules is easily produced via a simple process without requiring hot rolling and heat treatment processes. The surface of the foil is prevented from oxidizing and residual stress is not imparted to the foil. The productivity and the economic efficiency of the foil are improved.

Abstract: Disclosed are a method and an apparatus for producing a uranium foil with fine crystalline granules by forming the foil by the gravitational dropping of molten uranium or uranium alloy and rapidly cooling the foil by the contact with cooling rolls, and a foil produced thereby. In accordance with the present invention, a high-purity and high-quality uranium foil with an isotropic structure and fine crystalline granules is easily produced via a simple process without requiring hot rolling and heat treatment processes. The surface of the foil is prevented from oxidizing and residual stress is not imparted to the foil. The productivity and the economic efficiency of the foil are improved.

Abstract: The present invention is concerned with the fabrication process of low or high enrichment uranium and uranium alloy foil, and the fabrication apparatus therefor. Uranium (U) and uranium alloy [U—(A)Q—(B)X—(C)Y (Q: Al, Fe, Ni, Si, Cr, Zr element, X: Al, Fe, Ni, Si, Cr, Zr element, Y: Al, Fe, Ni, Si, Cr, Zr element, Q≠X≠Y, (A)≦1 wt %, (B)≦1 wt %, (C)≦1 wt %)] foil are directly obtained from a melt, not through a vacuum induction melting & casting, ingot cutting, hot-rolling and heat-treatment process, but through melt spinning or a twin-roll casting process. Major advantages have been obtained as follows: 1) a simplified process without the hot-rolling process and heat-treatment process, 2) an improvement in productivity and process economics in foil fabrication, and 3) a high purity and a high quality of the foil.