Korea Atomic Energy Research Institute

Agency for Defense Development

Korea Hydro Nuclear Power Co., Ltd.

Korea Electric Power Corporation

Seok-Jin Oh

Jun-Young Heo

Ki-Hwan Kim

Ji-Su Yoon

Jun Hwan Kim

Jin-Sik Cheon

Jong-Hyuk Baek

Chan Bock Lee

Jeong-Jin Kim

Young-Mo Ko

Seon-Uk Heo

Yoon-Myeong Woo

Ki Hwan Kim

Ho Jin Ryu

Sung-Ho Kim

Sung Ho Kim

Chang-Kyu Kim

Sun-Jae Kim

Tae-Kyu Kim

Dohee Hahn

Se-Jung Jang

Byoung-Oon Lee

Woo-Gon Kim

Il-Hyun Kuk

Seong-Hwan Bae

Chong-Tak Lee

Eung-Soo Kim

ByoungOon Lee

Seong Woo Yang

Junehyung Kim

Choong-Hwan Jung

Thae-Khapp Kang

Seong-Pil Joo

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.

Seawater flow control device for uniform motion

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.

Water-cooled flue gas collecting apparatus and wake treatment system including the same

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.

Thrust control apparatus of propulsion system

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.

Thrust control apparatus having inner and outer pintle nozzles controlled by common gear

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 &#x3bc;m to 100 &#x3bc;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.

Nuclear fuel rod for fast reactors including metallic fuel slug coated with protective coating layer and fabrication method thereof

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.

Nuclear fuel rod for fast reactors with oxide coating layer on inner surface of cladding, and manufacturing method thereof

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.

Method and apparatus for producing uranium foil and uranium foil produced thereby

The present invention provides silica balls in a spherical shape, the silica balls having a porous internal structure and a dense outside layer.

Light weight silica balls with a dense outer layer and method of making

Growing community of inventors

Daejeon, South Korea

Seok-Jin Oh