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31. 发明授权

EP3712601B1 METHOD FOR MEASURING DEGREE OF RECRYSTALLIZATION OF ZIRCONIUM ALLOY CLADDING TUBE FOR NUCLEAR FUEL BY USING EBSD PATTERN QUALITY 有权
公开(公告)号：EP3712601B1
公开(公告)日：2023-07-19
申请号：EP17932311.8
申请日：2017-12-15
发明人： JUNG, Tae Sik , MOK, Yong Kyoon , KIM, Yoon Ho , LEE, Chung Yong , JANG, Hun
IPC分类号： G01N23/203 , G01N23/20 , G01N23/205

32. 发明授权

EP3792614B1 APPARATUS FOR FATIGUE TESTING BULGE TOOL HAVING WH-TYPE SKELETON 有权
公开(公告)号：EP3792614B1
公开(公告)日：2023-04-05
申请号：EP18917739.7
申请日：2018-06-04
发明人： SON, Se Ick , KIM, In Kyu , PARK, Sung Jun , LEE, Je Won , SIM, Young Duk
IPC分类号： G01N3/32 , G01N3/08 , G01M99/00 , G21C3/334 , G21C17/06 , G21C3/34

33. 发明授权

EP3745418B1 NUCLEAR FUEL SINTERED BODY HAVING EXCELLENT IMPACT RESISTANCE 有权
公开(公告)号：EP3745418B1
公开(公告)日：2023-02-15
申请号：EP18901975.5
申请日：2018-07-30
发明人： NA, Yeon-soo , CHOI, Min Young , LIM, Kwang-young , LEE, Seung-jae , JUNG, Tae Sik , MOK, Yong Kyoon , YOO, Jong Sung
IPC分类号： B32B18/00 , C04B35/51 , G21C21/02 , G21C3/04 , C04B38/06 , G21C3/42 , G21C3/18 , G21C3/62 , C04B35/10

35. 发明公开

EP3712601A1 METHOD FOR MEASURING DEGREE OF RECRYSTALLIZATION OF ZIRCONIUM ALLOY CLADDING TUBE FOR NUCLEAR FUEL BY USING EBSD PATTERN QUALITY 有权
公开(公告)号：EP3712601A1
公开(公告)日：2020-09-23
申请号：EP17932311.8
申请日：2017-12-15
申请人： Kepco Nuclear Fuel Co., Ltd
发明人： JUNG, Tae Sik , MOK, Yong Kyoon , KIM, Yoon Ho , LEE, Chung Yong , JANG, Hun
IPC分类号： G01N23/203 , G01N23/20 , G01N23/205
摘要： The present invention particularly relates to a method for measuring the degree of recrystallization of a zirconium alloy cladding tube for a nuclear fuel by using EBSD pattern quality, and the objective of the present invention is to provide a method for measuring the degree of recrystallization of a zirconium alloy cladding tube for a nuclear fuel, the method being capable of more accurately obtaining a degree of recrystallization than a conventional method for calculating a degree of recrystallization by using pattern quality, by comprising: a first step of electrolytic polishing a fully recrystallized sample 1, a partially recrystallized sample 2 of which a recrystallization measurement is needed, and an As-deformed sample 3, then making an SEM electron beam incident to each of sample 1 to sample 3 at a predetermined scan interval, and then acquiring a backscattered electron signal through an EBSD camera; a second step of using EBSD software so as to convert the backscattered electron signals acquired from sample 1 to sample 3 into pattern quality values, and calculating the pattern quality values as frequencies within a specific range; a third step of obtaining a pattern quality frequency (B + D) deviated from a frequency of sample 3 among a total frequency distribution of sample 2 and obtaining a pattern quality frequency (D + E) deviated from the frequency of sample 3 among a total frequency distribution of sample 1; and a fourth step of obtaining a degree of recrystallization of sample 2 from equation X ′ = B + D D + E × 100 , %.

36. 发明公开

EP3660863A1 MOBILE EQUIPMENT FOR MEASURING STRUCTURAL DEFORMATION OF NUCLEAR FUEL ASSEMBLY 有权
公开(公告)号：EP3660863A1
公开(公告)日：2020-06-03
申请号：EP17919357.8
申请日：2017-09-29
申请人： Kepco Nuclear Fuel Co., Ltd
发明人： BAIK, Mun Seog , KIL, Gi Bong , CHANG, Kyung Hun
IPC分类号： G21C17/06 , G01B11/16
摘要： The present invention relates to mobile equipment for measuring structural deformation of a nuclear fuel assembly and, more particularly, to mobile equipment for measuring structural deformation of a nuclear fuel assembly, which measures the length, an envelope and a maximum slope of the nuclear fuel assembly, thereby enhancing the accuracy of measuring the structural deformation of the nuclear fuel assembly, and is configured in a container type so as to be moveable, thereby enhancing an operation efficiency for measurement locations. To this end, provided is mobile equipment for measuring structural deformation of a nuclear fuel assembly, comprising: a container; a power means and a loading stand which are disposed inside the container; a seat disposed at one side of the loading stand in the container and having a hinge means and a fixing means for fixing the nuclear fuel assembly upright; a column which is mounted on the loading stand and has a pivot shaft detachably coupled to the hinge means at one end thereof, wherein the column is erected upright on one side of the fixing means of the seat about the pivot shaft coupled to the hinge means by the power of the power means; and a scanner which is raised or lowered in the longitudinal direction of the column standing upright on the seat and which is for measuring structural deformation of the nuclear fuel assembly standing upright on the fixing means.

37. 发明公开

EP3633684A1 TREATMENT METHOD AND TREATMENT APPARATUS FOR URANIUM HEXAFLUORIDE RESIDUE WITHIN CYLINDER, USING GAS PHASE REACTION 有权转让
公开(公告)号：EP3633684A1
公开(公告)日：2020-04-08
申请号：EP17911945.8
申请日：2017-12-15
申请人： Kepco Nuclear Fuel Co., Ltd
发明人： BAE, Youngmoon , MOON, Yudon , HWANG, In-Kyu , SHIN, Hyundong , YANG, Seungchul , KWAK, Dongyong , LEE, Byungkook , CHO, Hyunkwang , LEE, Junho
IPC分类号： G21C21/02 , C01G43/06
摘要： The present invention relates to a treatment method and a treatment apparatus for UF 6 heel, using a gas phase reaction. A specific treatment method comprises the steps of: (1) vaporizing UF 6 heel; (2) generating solid UO 2 F 2 by using the vaporized UF 6 gas; (3) separating the solid UO 2 F 2 from a by-product gas; and (4) separating hydrogen fluoride from the by-product gas. The treatment apparatus can comprise: (1) a vaporizer used only for vaporizing UF 6 heel; (2) a reactor connected to the vaporizer so as to generate UO 2 F 2 by using the UF 6 gas generated at the vaporizer; (3) a solid/gas separator connected to the reactor so as to separate the solid UO 2 F 2 , which is generated in the reactor, from the by-product gas; (4) a heat exchanger connected to the solid/gas separator so as to allow the by-product gas, which is supplied from the solid/gas separator, to pass therethrough and be condensed into liquid; and (5) a liquid/gas separator for separating the hydrogen fluoride liquid, which is condensed at the heat exchanger, from the gas. According to the present invention, stabilization of a reconversion process and the quality of a UO 2 powder can be improved by preparing solid UO 2 F 2 , which is an intermediate of the UO 2 powder, through UF 6 heel treatment, and the high cost of radioactive waste disposal is reduced by minimizing UF 6 heel to be less than 0.5 kg.

38. 发明公开

EP3604256A1 SILICON CARBIDE SINTERED BODY HAVING OXIDATION RESISTANCE LAYER, AND METHOD FOR PRODUCING SAME 审中-实审
公开(公告)号：EP3604256A1
公开(公告)日：2020-02-05
申请号：EP18847183.3
申请日：2018-07-30
申请人： Kepco Nuclear Fuel Co., Ltd
发明人： LIM, Kwang-Young , LEE, Seung-Jae , NA, Yeon-Soo , JUNG, Tae Sik
IPC分类号： C04B35/575 , C04B35/63 , C04B35/626
摘要： Provided is a silicon-carbide-sintered body in which plural crystal grains including silicon carbide are densely formed so as to be adjacent to each other. Sc and Y elements are present in a rich phase at a triple point at which interfaces of the crystal grains forming the sintered body meet each other without solid-solution of the elements in the crystal grains. Accordingly, sintering is feasible at a temperature of 1950°C or lower, and an EB layer including a rare-earth-Si oxide containing the Sc and Y elements is formed on a surface thereof without an EB coating process, and is also formed up to the inner region of a silicon carbide base, resulting in strong three-dimensional bonding, so that the possibility of peeling of the EB layer is reduced and a new EB layer is formed even when peeling occurs, greatly increasing the resistance to corrosion of the silicon carbide material caused by oxidation. Further, the temperature at which the silicon carbide material is used is increased by preventing the oxidation of the silicon carbide material.

39. 发明公开

EP3241920A4 METHOD FOR MANUFACTURING NUCLEAR FUEL ZIRCONIUM PART BY USING MULTI-STAGE HOT-ROLLING 有权
公开(公告)号：EP3241920A4
公开(公告)日：2018-01-24
申请号：EP16882803
申请日：2016-01-29
申请人： KEPCO NUCLEAR FUEL CO LTD
发明人： MOK YONG KYOON , KIM YOON HO , JUNG TAE SIK , LEE SUNG YONG , JANG HUN , LEE CHUNG YONG , NA YEON SOO , CHOI MIN YOUNG , KO DAE GYUN , LEE SEUNG JAE , KIM JAE IK
IPC分类号： C22C16/00 , B21B3/00 , B21B37/16 , C22F1/18 , G21C21/00
CPC分类号： B21B3/00 , B21B37/16 , C22C16/00 , C22F1/18 , C22F1/186 , G21C21/00
摘要： Disclosed is a method of manufacturing a zirconium alloy component wherein precipitates having an average size of 35 nm or less are uniformly distributed in a matrix through multi-pass hot rolling, the method including forming an ingot of a niobium-containing zirconium alloy (step 1); subjecting the ingot obtained in step 1 to annealing at a zirconium beta-phase temperature and then rapid cooling (step 2); preheating the ingot rapidly cooled in step 2 before hot rolling (step 3); forming a multi-pass hot-rolled plate by performing primary hot rolling and then air cooling during which secondary hot rolling is subsequently conducted, immediately after the preheating in step 3 (step 4); subjecting the multi-pass hot-rolled plate obtained in step 4 to primary intermediate annealing and then primary cold rolling (step 5); subjecting the rolled plate, having undergone the primary cold rolling in step 5, to secondary intermediate annealing and then secondary cold rolling (step 6); subjecting the rolled plate, having undergone the secondary cold rolling in step 6, to tertiary intermediate annealing and then tertiary cold rolling (step 7); and subjecting the rolled plate, having undergone the tertiary cold rolling in step 7, to final annealing (step 8). The zirconium alloy plate manufactured in this way enables the formation of fine precipitates in the matrix, thus improving corrosion resistance under high-temperature water vapor conditions and increasing resistance to fatigue failure.

40. 发明公开

EP3241920A1 METHOD FOR MANUFACTURING NUCLEAR FUEL ZIRCONIUM PART BY USING MULTI-STAGE HOT-ROLLING 有权
标题翻译：利用多级热轧制造核燃料锆零件的方法
公开(公告)号：EP3241920A1
公开(公告)日：2017-11-08
申请号：EP16882803.6
申请日：2016-01-29
申请人： Kepco Nuclear Fuel Co., Ltd
发明人： MOK, Yong Kyoon , KIM, Yoon Ho , JUNG, Tae Sik , LEE, Sung Yong , JANG, Hun , LEE, Chung Yong , NA, Yeon Soo , CHOI, Min Young , KO, Dae Gyun , LEE, Seung Jae , KIM, Jae Ik
IPC分类号： C22C16/00 , C22F1/18 , B21B3/00 , B21B37/16 , G21C21/00
CPC分类号： C22F1/186 , B21B3/00 , B21B37/16 , C22C16/00 , C22F1/002 , C22F1/18 , G21C3/07 , G21C21/00
摘要： Disclosed is a method of manufacturing a zirconium alloy component wherein precipitates having an average size of 35 nm or less are uniformly distributed in a matrix through multi-pass hot rolling, the method including forming an ingot of a niobium-containing zirconium alloy (step 1); subjecting the ingot obtained in step 1 to annealing at a zirconium beta-phase temperature and then rapid cooling (step 2); preheating the ingot rapidly cooled in step 2 before hot rolling (step 3); forming a multi-pass hot-rolled plate by performing primary hot rolling and then air cooling during which secondary hot rolling is subsequently conducted, immediately after the preheating in step 3 (step 4); subjecting the multi-pass hot-rolled plate obtained in step 4 to primary intermediate annealing and then primary cold rolling (step 5); subjecting the rolled plate, having undergone the primary cold rolling in step 5, to secondary intermediate annealing and then secondary cold rolling (step 6); subjecting the rolled plate, having undergone the secondary cold rolling in step 6, to tertiary intermediate annealing and then tertiary cold rolling (step 7); and subjecting the rolled plate, having undergone the tertiary cold rolling in step 7, to final annealing (step 8). The zirconium alloy plate manufactured in this way enables the formation of fine precipitates in the matrix, thus improving corrosion resistance under high-temperature water vapor conditions and increasing resistance to fatigue failure.
摘要翻译：公开了一种制造锆合金部件的方法，其中平均尺寸为35nm或更小的沉淀物通过多道次热轧均匀分布在基体中，所述方法包括形成含铌锆合金锭（步骤1 ）; 对步骤1中获得的锭进行锆β相温度退火，然后快速冷却（步骤2）; 在热轧之前预热步骤2中快速冷却的锭（步骤3）; 在步骤3（步骤4）中的预热之后立即进行一次热轧然后进行二次热轧的空冷，形成多道次热轧板; 对步骤4中得到的多道次热轧板进行一次中间退火，然后进行一次冷轧（步骤5）; 对经过步骤5中的一次冷轧的轧制板进行二次中间退火和二次冷轧（步骤6）; 对经过步骤6中的二次冷轧的轧制板进行三次中间退火和三次冷轧（步骤7）; 并且将在步骤7中经过三次冷轧的轧制板进行最终退火（步骤8）。以这种方式制造的锆合金板能够在基体中形成微细的沉淀物，因此提高了高温水蒸气条件下的耐腐蚀性并且提高了耐疲劳破坏性。

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