Korea Atomic Energy Research Institute

Korea Hydro Nuclear Power Co., Ltd.

Hyun Gil Kim

Sang Yoon Park

Youn Ho Jung

Dong Jun Park

Jeong-Yong Park

Yang-Il Jung

Yang-Hyun Koo

Byoung-Kwon Choi

Jung Hwan Park

Il Hyun Kim

Byoung Kwon Choi

Yang Il Jung

Myung Ho Lee

Dong-Joo Kim

Jong Hyuk Baek

Jae-Ho Yang

Yong Hwan Jeong

Young Ho Lee

Jae Ho Yang

Jun Hwan Kim

Jeong Yong Park

Jihae Yoon

Heung Soo Lee

Jong Dae Hong

Disclosed are a method for coating metal, a metal member comprising the coating layer formed thereby, and a fuel cell separator. A method for coating metal according to an embodiment of the present invention includes preparing a metal base material; and forming a molten pool by irradiating a laser to a surface of the metal base material and forming a coating layer using an additive manufacturing by supplying a powder made of any one of Si, SiC, and a mixture of Cr and Al to the molten pool.

Method for coating metal, metal member comprising coating layer formed thereby and fuel cell separator

The present invention relates to a nuclear fuel pellet laminate structure having enhanced thermal conductivity, including a nuclear fuel pellet; and a thermally conductive metal layer disposed above or below the nuclear fuel pellet, and a method for manufacturing the same.

Nuclear fuel pellet laminate structure having enhanced thermal conductivity and method for manufacturing the same

The present invention relates to a zirconium alloy cladding with improved oxidation resistance at a high temperature and a method of manufacturing the same. More particularly, the zirconium alloy cladding includes a zirconium alloy cladding; and a Cr&#x2014;Al thin film coated on the cladding, wherein the thin film is deposited through arc ion plating and the content of Al in the thin film is 5% by weight to 20% by weight.

Zirconium alloy cladding with improved oxidation resistance at high temperature and method for manufacturing same

The present disclosure relates to a chromium-aluminum binary alloy with excellent corrosion resistance and a method of producing the same, and more particularly to a chromium-aluminum binary alloy with excellent corrosion resistance. The chromium-aluminum binary alloy may be easily produced and has ductility, thus being highly applicable as a coating material for a material requiring high-temperature corrosion resistance and wear resistance.

Chromium-aluminum binary alloy having excellent corrosion resistance and method of manufacturing thereof

An oxide dispersion strengthening (ODS) method of a metallic material using a laser is provided, which includes melting a surface of a metallic matrix placed on a movable stage by irradiating a laser onto the surface (step 1), supplying an oxide dispersion strengthening (ODS) powder at a site of the matrix surface which is melt at step 1 (step 2), and cooling the matrix in which the ODS powder is supplied at step 2 (step 3). Because oxide particles are directly supplied into previously-made sheet or tube matrix, fabrication process is simplified, fabrication cost is reduced, and end product is fabricated efficiently.

Method for oxide dispersion strengthening of metallic material using laser

Disclosed are a zirconium alloy for a nuclear fuel cladding having a good corrosion resistance by reducing an amount of alloying elements and a method of preparing a zirconium alloy nuclear fuel cladding using thereof. The zirconium alloy includes 0.2 to 0.5 wt % of niobium (Nb); 0.2 to 0.6 wt % of iron (Fe); 0.3 to 0.5 wt % of chromium (Cr); 0.1 to 0.15 wt % of oxygen (O); 0.008 to 0.012 wt % of silicon (Si) and a remaining amount of zirconium (Zr). The total amount of the niobium, the iron and the chromium is 1.1 to 1.2 wt %. A good oxidation resistance of the nuclear fuel cladding may be confirmed under accident conditions as well as normal operating conditions of a reactor, thereby improving economic feasibility and safety.

Zirconium alloys for a nuclear fuel cladding having a superior corrosion resistance by reducing an amount of alloying elements and methods of preparing a zirconium alloy nuclear fuel cladding using thereof

Disclosed are a zirconium alloy for a nuclear fuel cladding having a good oxidation resistance in a severe reactor operation condition and a method of preparing zirconium alloy nuclear fuel claddings by using thereof. The zirconium alloy includes 1.8 to 2.0 wt % of niobium (Nb); at least one element selected from iron (Fe), chromium (Cr) and copper (Cu); 0.1 to 0.15 wt % of oxygen (O); 0.008 to 0.012 wt % of silicon (Si) and a remaining amount of zirconium (Zr). The amount of Fe is 0.1 to 0.4 wt %, the amount of Cr is 0.05 to 0.2 wt %, and the amount of Cu is 0.03 to 0.2 wt %. A good oxidation resistance of the nuclear fuel cladding may be confirmed under a severe reactor operation condition at an accident condition as well as a normal operating condition of a reactor, thereby improving economic efficiency and safety.

Zirconium alloys for a nuclear fuel cladding having a superior oxidation resistance in a severe reactor operation condition and methods of preparing a zirconium alloy nuclear cladding by using thereof

Disclosed are a zirconium alloy for a nuclear fuel cladding having a good oxidation resistance in reactor accident conditions, a zirconium alloy nuclear fuel cladding prepared by using thereof and a method of preparing the same. The zirconium alloy includes 1.0 to 1.2 wt % of niobium (Nb); at least one element selected from tin (Sn), iron (Fe) and chromium (Cr); 0.02 to 0.1 wt % of copper (Cu); 0.1 to 0.15 wt % of oxygen (O); 0.008 to 0.012 wt % of silicon (Si) and a remaining amount of zirconium (Zr). The amount of Sn is 0.1 to 0.3 wt %, the amount of Fe is 0.3 to 0.8 wt %, and the amount of Cr is 0.1 to 0.3 wt %. A good oxidation resistance of the nuclear fuel cladding may be confirmed under accident conditions as well as normal operating conditions of a reactor, thereby improving economic efficiency and safety.

Zirconium alloys for a nuclear fuel cladding having a superior oxidation resistance in a reactor accident condition, zirconium alloy nuclear fuel claddings prepared by using thereof and methods of preparing the same

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.

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Daejeon, South Korea

Hyun Gil Kim