Patent application number | Description | Published |
20100108204 | ZIRCONIUM ALLOY COMPOSITION FOR NUCLEAR FUEL CLADDING TUBE FORMING PROTECTIVE OXIDE FILM, ZIRCONIUM ALLOY NUCLEAR FUEL CLADDING TUBE MANUFACTURED USING THE COMPOSITION, AND METHOD OF MANUFACTURING THE ZIRCONIUM ALLOY NUCLEAR FUEL CLADDING TUBE - Disclosed herein is a zirconium alloy composition for nuclear fuel cladding tubes, comprising: 1.6˜2.0 wt % of Nb; 0.05˜0.14 wt % of Sn; 0.02˜0.2 wt % of one or more elements selected from the group consisting of Fe, Cr and Cu; 0.09˜0.15 wt % of O; 0.008˜0.012 wt % of Si; and a balance of Zr, a nuclear fuel cladding tube comprising the zirconium alloy composition, and a method of manufacturing the nuclear fuel cladding tube. Since the nuclear fuel cladding tube made of the zirconium alloy composition can maintain excellent corrosion resistance by forming a protective oxide film thereon under the conditions of high-temperature and high-pressure cooling water and water vapor, it can be usefully used as a nuclear fuel cladding tube for light water reactors or heavy water reactors, thus improving the economical efficiency and safety of the use of nuclear fuel. | 05-06-2010 |
20100322370 | PROCESS OF MANUFACTURING ZIRCONIUM ALLOY FOR FUEL GUIDE TUBE AND MEASURING TUBE HAVING HIGH STRENGTH AND EXCELLENT CORROSION RESISTANCE - A process of manufacturing zirconium alloy. The process may be used to make a nuclear fuel guide tube and/or a measuring tube which are main components of a nuclear fuel assembly structure. While a nuclear fuel guide tube and a measuring tube are manufactured by performing three-step cold working, and intermediate and final thermal annealing from a semi-finished TREX shell in the conventional method, the present invention relates to zirconium alloy undergoing two-step cold working, and intermediate and final thermal annealing from a TREX shell, resulting in enhanced strength and corrosion resistance. The present invention may be applied to a nuclear fuel guide tube and a measuring tube used for a nuclear fuel assembly in a light water nuclear reactor because, by the shortened process, high percentage reduction in thickness between processes and an decrease in thermal annealing time may sustain high strength and excellent corrosion resistance, and achieve economy of manufacture by reducing the number of processes. | 12-23-2010 |
20120145287 | ZIRCONIUM ALLOY COMPOSITIONS HAVING EXCELLENT CORROSION RESISTANCE BY THE CONTROL OF VARIOUS METAL-OXIDE AND PRECIPITATE AND PREPARATION METHOD THEREOF - Disclosed herein are a zirconium alloy composition, which exhibits excellent corrosion resistance by varying the kinds of metal oxides and controlling the size of precipitates of the composition, including: 1.05˜1.45 wt % of Nb; one or more selected from the group consisting of 0.1˜0.7 wt % of Fe and 0.05˜0.6 wt % of Cr; and residual Zr, and a method of preparing the same. The zirconium alloy composition exhibits excellent corrosion resistance by controlling the kinds and amounts of the elements included in the zirconium alloy composition and the heat-treatment temperature and thus varying the kinds of metal oxides formed during an oxidation process and controlling the size of precipitates of the zirconium alloy, so that it can be usefully used as a raw material for nuclear fuel cladding tubes, spacer grids, nuclear reactor internals and the like of a light-water reactor or a heavy-water reactor in a nuclear power plant. | 06-14-2012 |
20130220493 | 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 - 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 (0); 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. | 08-29-2013 |
20130220494 | 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 CALDDING USING THEREOF - 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. | 08-29-2013 |
20130220495 | 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 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. | 08-29-2013 |
20130299470 | Method for oxide dispersion strengthening of metallic material using laser - 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. | 11-14-2013 |
20130302639 | ZIRCONIUM ALLOY FOR IMPROVING RESISTANCE TO OXIDATION AT VERY HIGH TEMPERATURE AND FABRICATION METHOD THEREOF - A zirconium alloy for use in nuclear fuel assemblies is provided, which provides increased resistance against oxidation and corrosion and also improved bonding with parent material, because pure metallic material such as silicon (Si) or chromium (Cr) is evenly coated on the surface of the parent material by plasma spraying. Because the plasma spray coating used to coat the pure metallic material on the zirconium alloy does not require vacuum equipment and also is not limited due to the shape of the coated product, this is particularly useful when evenly treating the surface of the component such as 4 m-long tube or spacer grip arrangement which is very complicated in shape. Furthermore, because the coated zirconium alloy confers excellent resistance to oxidation and corrosion under emergency such as accident as well as normal service condition, both the economic and safety aspects of nuclear fuel are improved. | 11-14-2013 |
20130344348 | ZIRCONIUM ALLOY WITH COATING LAYER CONTAINING MIXED LAYER FORMED ON SURFACE, AND PREPARATION METHOD THEREOF - A zirconium alloy with a coating layer formed on a surface comprising a mixed layer, the mixed layer comprises one or more very high temperature oxidation resistant material and zirconium alloy parent material selected from the group consisting of Y | 12-26-2013 |