Korea Atomic Energy Research Institute

Jun-Hwan Kim

Jong-Hyuk Baek

Chan-Bock Lee

Sung-Ho Kim

Jin-Sik Cheon

Tae-Kyu Kim

Do-Hee Hahn

Woo-Gon Kim

Byoung-Oon Lee

Chang-Hee Han

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

Growing community of inventors

Daejeon, South Korea

Jun-Hwan Kim