Korea Atomic Energy Research Institute

Korea Hydro Nuclear Power Co., Ltd.

Jong-Hyuk Baek

Jin-Sik Cheon

Seok-Jin Oh

Sung-Ho Kim

Jun Hwan Kim

Chan Bock Lee

Tae-Kyu Kim

Woo-Gon Kim

Young-Mo Ko

Yoon-Myeong Woo

Chan-Bock Lee

Jun-Hwan Kim

Byoung-Oon Lee

Ki Hwan Kim

Ki-Hwan Kim

Ho Jin Ryu

Sung Ho Kim

Dohee Hahn

Do-Hee Hahn

Chang-Hee Han

ByoungOon Lee

Chong-Tak Lee

Junehyung Kim

Seong Woo Yang

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

A nuclear fuel rod for a fast reactor is provided, in which a reactor core of the fast reactor can be designed compact-sized by reducing the length of the nuclear fuel rod to be smaller than the length of a conventional one. The nuclear fuel rod for a fast reactor includes a tubular fuel materials comprising a hollow portion formed therein, a tubular inner pipe inserted into the hollow portion of the tubular fuel materials to prevent collapse of the tubular fuel materials due to combustion of nuclear fuel, a tubular cladding pipe which surrounds the tubular fuel materials, and a liquid metal, or He gas or vacuum applied in a gap between the tubular fuel materials and the tubular cladding pipe, and the tubular inner pipe includes a collecting space formed therein to collect fission products such as fission gas which are generated due to combustion of the nuclear fuel.

Nuclear fuel rod for fast reactor

Provided is a method of manufacturing a high strength ferritic/martensitic steel. The method includes melting a ferritic/martensitic steel, hot-working the melted ferritic/martensitic steel, normalizing the hot-worked ferritic/martensitic steel at a temperature of about 1050&#xb0; C. to about 1200&#xb0; C., tempering the ferritic/martensitic steel at a temperature of about 600&#xb0; C. or less, and leaving MX precipitates while preventing a MCprecipitate from being precipitated, and cold-working and thermal-treating the ferritic/martensitic steel in a multistage fashion, and precipitating MCprecipitates. Through the above described configuration, the high strength ferritic/martensitic steel that prevents a ductility from being deteriorated even in a high-temperature environment may be manufactured.

Manufacturing method of high strength ferritic/martensitic steels

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

Growing community of inventors

Daejeon, South Korea

Jong-Hyuk Baek