Patent application number | Description | Published |
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 |
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 |
20130223582 | FABRICATION METHOD OF BURNABLE ABSORBER NUCLEAR FUEL PELLETS AND BURNABLE ABSORBER NUCLEAR FUEL PELLETS FABRICATED BY THE SAME - A fabrication method of burnable absorber nuclear fuel pellets and burnable absorber nuclear fuel pellets fabricated by the same are provided, in which the fabrication method includes adding boron compound and manganese compound to one or more type of nuclear fuel powders selected from the group consisting of uranium dioxide (UO | 08-29-2013 |
20130264222 | MONITORING METHOD AND SYSTEM OF METAL IONS OR OXYGEN IONS APPLICABLE TO HIGH CONCENTRATION NON-AQUEOUS ELECTROLYTE - A monitoring method of metal ions or oxygen ions applicable to a high concentration non-aqueous electrolyte includes: applying a potential in a non-aqueous electrolyte to obtain current information with respect to the potential; varying the potential applied in the non-aqueous electrolyte containing metal ion concentration or oxygen ion concentration such that the metal ion concentration or the oxygen ion concentration is maintained in spite of the potential being applied; detecting a linear relationship among the concentration, the current, and passed charges in the non-aqueous electrolyte by repeatedly performing the obtaining step and the varying step, while changing the concentration; and calculating metal ion concentration or oxygen ion concentration of the non-aqueous electrolyte in pyroprocessing of the non-aqueous electrolyte by using the linear relationship. Concentration and components of a solute existing in a non-aqueous electrolyte can be measured while an electrowinning process and pyroprocessing is being conducted. | 10-10-2013 |
20130266992 | COMPOSITION FOR INCREASING SACCHARIFICATION EFFICIENCY OF BIOMASS, METHOD FOR INCREASING SACCHARIFICATION EFFICIENCY OF BIOMASS AND METHOD FOR PREPARING BIOETHANOL DERIVED FROM BIOMASS ON A LARGE SCALE USING CHAPERONE PROTEIN - The present invention relates to a novel method for increasing saccharification efficiency by adding chaperone protein during saccharification process, more precisely a composition for increasing saccharification efficiency of biomass containing cellulose using peroxiredoxin (Prx) protein and a method for increasing glucose yield by using the same. The conventional saccharification process has the disadvantage of decreasing cellulase activity, suggesting that the high priced saccharogenic enzyme has to be continuously supplied since the saccharogenic enzyme is losing its activity continuously by reducing sugar through the whole saccharification process. Therefore, to increase saccharification efficiency, the present invention provides a method characterized by increasing saccharification efficiency by preventing cellulase from losing its activity throughout the whole saccharification process by using chaperone protein, particularly Prx protein herein, together with cellulase. The method of the present invention, therefore, can overcome the disadvantage of the conventional saccharification process. | 10-10-2013 |
20130302244 | METHOD OF PREPARING IODINE SEED FOR TREATING EYE DISEASE OR CANCER, AND IODINE SEED PREPARED THEREBY - The present invention provides a technique for adsorbing I-125 on a support for treating cancer and a method of preparing an I-125 seed using the same. Since a method of preparing iodine according to the present invention uses an intermediate having phosphate-based, oxalate-based, or arsenate-based anions introduced thereinto, the intermediate has a substitution effect of iodine 3 to 5 times higher than that of a typically used intermediate having chlorine anions introduced thereinto. According to the substitution effect, control of a radiation dose may be possible during the manufacturing of an iodine seed and an iodine seed may be prepared within a shorter period of time. Also, since an amount of residual radioactive iodine may be decreased as a result of a large amount of adsorption, an amount of radioactive iodine (I-125) waste may be decreased, and the effect thereof may be also high environmentally. | 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 |
20130343504 | HEAT EXCHANGER FOR PASSIVE RESIDUAL HEAT REMOVAL SYSTEM - Disclosed is a heat exchanger for a passive residual heat removal system, which improves heat transfer efficiency by expanding a heat transfer area. A heat exchange tube includes a first member connected to a steam pipe through which steam generated from a steam generator of a nuclear reactor circulates, and a second member connected to both of the first member and a feed water pipe used to supply water to the steam generator provided in the nuclear reactor, and the first member has the shape different from that of the second member, thereby expanding the heat transfer area so that the heat transfer efficiency is improved. | 12-26-2013 |
20140016732 | APPARATUS AND METHOD FOR CONTROLLING CONTROL ROD OF NUCLEAR REACTOR FOR NUCLEAR POWER PLANT - An apparatus and method for safely controlling a control rod of a nuclear reactor for a nuclear power plant is provided. The apparatus may include a first controller to output a signal to insert or withdraw the control rod, a mechanical portion to perform insertion or withdrawal of the control rod in response to the signal output by the first controller, the mechanical portion including a movement process portion, a stop latch to restrain the control rod, a moving latch to move the control rod, and a lift coil to insert or withdraw the control rod, a detector to detect a position or a speed of the control rod when the control rod is inserted or withdrawn, and a brake to stop the control rod by force when the control rod is withdrawn irrespective of an intended control of the control rod. | 01-16-2014 |
20140048020 | TUBE SHEET OF STEAM GENERATOR HAVING ANTICORROSIVE LAYER AND MANUFACTURING METHOD THEREOF - Provided are a tube sheet of a steam generator installed to support a tube of the steam generator, and a manufacturing method thereof, particularly, a tube sheet of a steam generator having an anticorrosive layer and a manufacturing method thereof. | 02-20-2014 |
20140080217 | Uranium Analysis Using Luminescence Enhancing Oxidant and Oxidant Composition - According to the present invention, there is provided a method of determining a concentration of uranium including: a) a primary measuring step of measuring luminescence intensity or luminescence attenuation of uranium (VI) of an oxidant added sample obtained by adding an oxidant composition to a detection target sample; b) a secondary measuring step of adding different volumes of standard solution containing uranium (VI) having a predetermined concentration to a plurality of oxidant added samples, respectively, and then measuring luminescence intensity or luminescence attenuation of uranium (VI) contained in each standard solution added sample; and c) a calculating step of calculating a concentration of uranium (VI) contained in the detection target sample by a standard addition method based on the primary and secondary measurements. With the method for determining a concentration of uranium according to the present invention, the concentration of uranium may be further rapidly and accurately analyzed. | 03-20-2014 |