Korea Atomic Energy Research Institute

Korea Hydro Nuclear Power Co., Ltd.

Jun Hwan Kim

Ki Hwan Kim

Ki-Hwan Kim

Sang Yoon Park

Youn Ho Jung

Chan Bock Lee

Jin-Sik Cheon

Jong Hyuk Baek

Seok-Jin Oh

Sung Ho Kim

Jong-Hyuk Baek

Dohee Hahn

Yoon-Myeong Woo

Young-Mo Ko

Ho Jin Ryu

Tae Kyu Kim

Myung Ho Lee

Yong Hwan Jeong

Hyun Gil Kim

Sung-Ho Kim

Byoung Kwon Choi

Tae-Kyu Kim

Jeong Yong Park

Woo-Gon Kim

Byoung-Oon Lee

Yeong-Il Kim

Chong-Tak Lee

Woo Gon Kim

Junehyung Kim

Seong Woo Yang

ByoungOon Lee

Chang Hee Han

Je Geon Bang

The present invention provides a dry interim storage container for spent nuclear fuel, precisely a dry interim storage container that can be filled with spent nuclear fuel wherein the storage container space is also filled with metal particles. The dry storage container for spent nuclear fuel of the present invention is filled with particles in its empty space for the spent nuclear fuel, which is advantageous in cooling efficiency and maintenance cost, compared with the conventional storage method using gas.

Storage container for spent nuclear fuel

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).

High Cr ferritic/martensitic steels having an improved creep resistance for in-core component materials in nuclear reactor, and preparation method thereof

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

A high Fe-containing zirconium composition having excellent corrosion resistance and a preparation method thereof. Specifically, disclosed are a high Fe-containing zirconium composition having excellent corrosion resistance and a preparation method thereof, the composition comprising: 0.5-1.0 wt % iron; 0.25-0.5 wt % chromium; 0.06-0.18 wt % oxygen; at least one element selected from the group consisting of 0.2-0.5 wt % tin, 0.1-0.3 wt % niobium and 0.05-0.3 wt % copper; and the balance of zirconium. The zirconium alloy has excellent corrosion resistance, and thus can be used as a material for nuclear fuel claddings, spacer grids and nuclear reactor core structures in light water reactor and heavy water reactor nuclear power plants.

High Fe contained zirconium alloy compositions having excellent corrosion resistance and preparation method thereof

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Daejeon, South Korea

Jun Hwan Kim