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1. 发明公开

EP4249454A2 SOLIDIFYING-AGENT COMPOSITION CONTAINING ALUMINA CEMENT FOR SOLIDIFYING RADIOACTIVE WASTE 审中-实审
公开(公告)号：EP4249454A2
公开(公告)日：2023-09-27
申请号：EP23191067.0
申请日：2016-06-17
申请人： Kepco Nuclear Fuel Co., Ltd
发明人： CHO, Nam-Chan , JU, Young-Jong , KIM, Jeong-Myeong , LIM, Dong Han , KI, Kyoung Kuk , PARK, Jung Hoon
IPC分类号： C04B111/00
摘要： The present invention relates to a solidifying agent for solidifying radioactive waste, and the solidifying-agent composition for solidifying radioactive waste of the present invention comprises alumina cement and a gypsum powder. According to the present invention, a solidifying-agent composition containing alumina cement and a gypsum powder is provided, leading to an effect of minimizing the volume increase of a radioactive waste solidified body at a level that meets physical and chemical safety regulations in the solidification treatment of radioactive waste.

2. 发明公开

EP3709312A1 SYSTEM FOR DECOUPLING AND COUPLING UPPER END FITTING OF NUCLEAR FUEL ASSEMBLY 审中-公开
公开(公告)号：EP3709312A1
公开(公告)日：2020-09-16
申请号：EP17931261.6
申请日：2017-11-17
申请人： Kepco Nuclear Fuel Co., Ltd
发明人： CHUN, Joo Hong , KIM, Seong Soo , KIM, Ba Leum , RYU, Su Pil , PARK, Nam Gyu , YOO, Jong Sung
IPC分类号： G21C3/33
摘要： Disclosed is a system for decoupling and coupling an upper end fitting of a nuclear fuel assembly. In the present invention, a lock insert, which is coupled to a guide hole formed on a flow channel plate of an upper end fitting of a nuclear fuel assembly and supports the upper end fitting, is characterized by comprising: a hollow body; and an insertion part provided in an upper portion of the body and inserted into the guide hole, wherein the insertion part is inserted into the guide hole by varying the circumference of the insertion part. According to the present invention, disassembly and reassembly of the upper end fitting of the nuclear fuel assembly and the lock insert are simplified to simplify and reduce the number of processes involved, and thus the system is effective for the maintenance and repair of the nuclear fuel assembly.

3. 发明公开

EP3293737A1 CORRELATION TOLERANCE LIMIT SETTING SYSTEM USING REPETITIVE CROSS-VALIDATION AND METHOD THEREFOR 有权
标题翻译：使用重复交叉验证的相关公差容限设定系统及其方法
公开(公告)号：EP3293737A1
公开(公告)日：2018-03-14
申请号：EP16898012.6
申请日：2016-04-26
申请人： Kepco Nuclear Fuel Co., Ltd
发明人： KIM, Kang Hoon , KIM, Byeung Seok , NAHM, Kee Yil
IPC分类号： G21C17/10
CPC分类号： G21C17/10 , G05B13/0265 , G21D3/001 , Y02E30/40
摘要： The present invention relates to a correlation tolerance limit setting system using repetitive cross-validation and a method therefor and, to a correlation tolerance limit setting system using repetitive cross-validation and a method therefor, the system and the method being for preventing data characteristic distortion due to accidental or human interference in correlation optimization and tolerance limit setting, and for preventing a risk created thereby, or for quantifying the influence thereof. According to the present invention, the correlation tolerance limit setting system using repetitive cross-validation comprises: a variable extraction unit for classifying training sets and validation sets, and optimizing a correlation coefficient so as to extract variables; a normality verification unit for verifying normality in accordance with the variable extraction result; a DNBR limit unit for verifying whether the same population is present according to the normality, and determining a tolerance limit of a departure from a nucleate boiling ratio by using a tolerance limit distribution for a departure from nucleate boiling; and a control unit.
摘要翻译：本发明涉及一种使用重复交叉验证的相关容限限制设定系统及其方法，并且涉及一种使用重复交叉验证的相关容限限制设定系统及其方法，所述系统和方法用于防止数据特征失真由于意外或人为干扰相关性优化和容限限制设定，并防止由此产生的风险或量化其影响。根据本发明，使用重复交叉验证的相关容限极限设置系统包括：变量提取单元，用于对训练集合和验证集合进行分类，并优化相关系数以提取变量; 正态验证单元，用于根据所述可变提取结果验证正态性; DNBR限制单元，用于根据正常情况验证是否存在相同的总体，并且通过使用偏离核沸腾的容限限制分布来确定与核沸腾比的偏离的容限; 和一个控制单元。

4. 发明公开

EP3284836A1 ZIRCONIUM ALLOY HAVING EXCELLENT CORROSION RESISTANCE AND CREEP RESISTANCE, AND METHOD FOR MANUFACTURING SAME 有权
标题翻译：具有优异的耐腐蚀性和抗蠕变性的锆合金及其制造方法
公开(公告)号：EP3284836A1
公开(公告)日：2018-02-21
申请号：EP15889277.8
申请日：2015-05-08
申请人： Kepco Nuclear Fuel Co. Ltd.
发明人： CHOI, Min Young , MOK, Yong Kyoon , KIM, Yoon Ho , NA, Yeon Soo , LEE, Chung Yong , JUNG, Tae Sik , KO, Dae Gyun , LEE, Seung Jae , KIM, Jae Ik
IPC分类号： C22C16/00 , C22F1/18 , B21B3/00
CPC分类号： C22C16/00 , B22D7/005 , B22F1/00 , C22C1/02 , C22F1/186
摘要： The present invention provides a zirconium alloy containing 1.1-1.2 wt% of niobium, 0.01-0.2 wt% of phosphorous, 0.2-0.3 wt% of iron and a remainder made up by zirconium, and a method for manufacturing a zirconium alloy having excellent corrosion resistance performance and a resistance performance against creep deformation, the method comprising: a first step of manufacturing an ingot by dissolving the mixture which constitutes the zirconium alloy; a second step of solution heat treating the ingot manufactured in the first step at 1,000-1,050°C (β-phase interval) for 30-40 minutes, then rapidly cooling same in water and β-quenching same; a third step of preheating the ingot which was heat-treated in the second step at 630-650°C for 20-30 minutes, then hot-rolling same at a reduction ratio of 60-65%; a fourth step of performing primary intermediate vacuum heat treatment on the hot-rolled material in the third step at 570-590°C for 3-4 hours, then performing primary cold-rolling on same at a reduction ratio of 30-40%; a fifth step of performing secondary intermediate vacuum heat treatment on the primarily cold-rolled material in the fourth step at 560-580°C for 2-3 hours, then performing secondary cold-rolling on same at a reduction ratio of 50-60%; a sixth step of performing tertiary intermediate vacuum heat treatment on the secondarily cold-rolled material in the fifth step at 560-580°C for 2-3 hours, then performing tertiary cold-rolling on same at a reduction ratio of 30-40%; and a seventh step of performing final vacuum heat treatment on the tertiarily cold-rolled material in the sixth step at 440-650°C for 7-9 hours.
摘要翻译：本发明提供一种含有1.1〜1.2重量％的铌，0.01〜0.2重量％的磷，0.2〜0.3重量％的铁，剩余部分由锆构成的锆合金以及具有优异的耐腐蚀性的锆合金的制造方法所述方法包括：第一步骤，通过溶解构成所述锆合金的所述混合物来制造锭;以及第二步骤，第二步将第一步制得的晶锭在1000〜1050℃（β相间隔）下固溶加热处理30〜40分钟，然后在水中快速冷却并β-淬灭; 在第二步骤中将在630-650℃热处理20-30分钟的锭料预热的第三步骤，然后以60-65％的压下比率对其进行热轧; 第四步骤，在第三步骤中在570-590℃下对热轧材料进行初步中间真空热处理3-4小时，然后以30-40％的压下率对其进行初次冷轧; 第五步骤，在第四步骤中在560-580℃对所述一次冷轧材料进行二次中间真空热处理2-3小时，然后以50-60％的压下率对其进行二次冷轧， ; 第五步骤，在第五步骤中在560-580℃下对第二次冷轧材料进行第二次中间真空热处理2-3小时，然后以30-40％的压下率对其进行三次冷轧， ; 以及第六步骤，在第六步骤中对第三步骤的冷轧材料在440-650℃进行最终真空热处理7-9小时。

5. 发明公开

EP3282452A1 METHOD OF ANALYZING THE SINTERED DENSITY OF URANIUM OXIDE (UOX) USING SPECTROPHOTOMETER 有权
标题翻译：用分光光度计分析氧化铀烧结密度的方法
公开(公告)号：EP3282452A1
公开(公告)日：2018-02-14
申请号：EP16202658.7
申请日：2016-12-07
申请人： Kepco Nuclear Fuel Co., Ltd
发明人： YOUNGMOON, Bae , YANG, Seungchul , BYUNGKUK, Lee , KWAK, Dongyong , CHO, Hyunkwang , GU, Sunghoi , HWANG, Euijun
IPC分类号： G21C3/62 , G21C19/46 , G21C21/02 , G01J3/28 , G01N21/55
CPC分类号： G01N33/222 , G01N9/24 , G01N21/25 , G01N21/31 , G01N2033/0091 , G01N2033/0093 , G21C3/26 , G21C3/623 , G21C17/06 , G21C19/46 , G21C21/02 , G21C2003/045 , Y02E30/38 , Y02W30/883
摘要： Disclosed is a method of predicting, calculating, or analyzing the sintered density of uranium oxide (UO x ) before uranium oxide is added in the pelletizing process during a process of manufacturing nuclear fuel, the method including measuring the chromaticity of ammonium diuranate using a spectrophotometer. The present invention provides a simple and highly reliable method of predicting the sintered density of uranium oxide (UO x ), which overcomes the problem with a conventional technology where the sintered density of uranium oxide (UO x ) can be analyzed only in a pellet state and a subsequent treatment process needs to be performed according to the analysis result.
摘要翻译：本发明公开了一种在制造核燃料的过程中在造粒过程中添加氧化铀之前预测，计算或分析氧化铀（UO x）的烧结密度的方法，该方法包括使用分光光度计测量重铀酸铵的色度。本发明提供了一种简单且高度可靠的预测氧化铀（UO x）的烧结密度的方法，其克服了常规技术中的问题，其中氧化铀的氧化铀（UO x）的烧结密度仅可以在颗粒状态和需要根据分析结果进行后续的处理过程。

6. 发明授权

EP3035339B1 METHOD OF SYNTHESIZING AXIAL POWER DISTRIBUTIONS OF NUCLEAR REACTOR CORE USING NEURAL NETWORK CIRCUIT AND IN-CORE PROTECTION SYSTEM (ICOPS) USING THE SAME 有权
标题翻译：利用神经网络电路和核心保护系统（ICOPS）合成核反应堆堆芯轴向功率分布的方法
公开(公告)号：EP3035339B1
公开(公告)日：2017-12-13
申请号：EP15182971.0
申请日：2015-08-28
申请人： Kepco Nuclear Fuel Co., Ltd
发明人： Park, Young Ho , Kim, Young Baek , Kim, Dong Soo , Oh, Do Young
IPC分类号： G21D3/00 , G06N3/02
CPC分类号： G21C17/06 , G06G7/54 , G06N3/088 , G21D3/00 , G21D3/10 , G21D2003/002 , Y02E30/39
摘要： There are provided a method of synthesizing axial power distributions of a nuclear reactor core using a neural network circuit and an in-core protection system (ICOPS) using the same, in which using the neural network circuit including an input layer, an output layer, and at least one hidden layer, each layer being configured with at least one node, each node of one layer being connected to nodes of the other layers, node-to-node connections being made with connection weights varied based on a learning result, optimum connection weights between the respective nodes constituting the neural network circuit are determined through learning based on various core design data applied to the design of a nuclear reactor core of a nuclear power plant, and axial power distributions of the nuclear reactor core are synthesized based on ex-core flux detector signals measured by ex-core neutron flux detectors during operation of a nuclear reactor, so that the initial time required to perform a start-up test of the nuclear reactor can be reduced since basic data for synthesizing axial power distributions need not be separately measured in the start-up test of the nuclear reactor contrary to a conventional ICOPS, thereby improving the economic efficiency of the nuclear power plant, and so that overall nuclear reactor core design data can be used rather than actual measurement data in the start-up test (i.e., at the beginning of a period of nuclear fuel), thereby more accurately replicating axial power distributions of the nuclear reactor core throughout the overall period of the nuclear fuel.

7. 发明公开

EP3035339A1 METHOD OF SYNTHESIZING AXIAL POWER DISTRIBUTIONS OF NUCLEAR REACTOR CORE USING NEURAL NETWORK CIRCUIT AND IN-CORE PROTECTION SYSTEM (ICOPS) USING THE SAME 有权
标题翻译：工艺对于使用神经网络连接，并且核心保护系统（ICOPS）核反应堆的核心性能轴向分布的制备SO
公开(公告)号：EP3035339A1
公开(公告)日：2016-06-22
申请号：EP15182971.0
申请日：2015-08-28
申请人： Kepco Nuclear Fuel Co., Ltd
发明人： Park, Young Ho , Kim, Young Baek , Kim, Dong Soo , Oh, Do Young
IPC分类号： G21D3/00 , G06N3/02
CPC分类号： G21C17/06 , G06G7/54 , G06N3/088 , G21D3/00 , G21D3/10 , G21D2003/002 , Y02E30/39
摘要： There are provided a method of synthesizing axial power distributions of a nuclear reactor core using a neural network circuit and an in-core protection system (ICOPS) using the same, in which using the neural network circuit including an input layer, an output layer, and at least one hidden layer, each layer being configured with at least one node, each node of one layer being connected to nodes of the other layers, node-to-node connections being made with connection weights varied based on a learning result, optimum connection weights between the respective nodes constituting the neural network circuit are determined through learning based on various core design data applied to the design of a nuclear reactor core of a nuclear power plant, and axial power distributions of the nuclear reactor core are synthesized based on ex-core flux detector signals measured by ex-core neutron flux detectors during operation of a nuclear reactor, so that the initial time required to perform a start-up test of the nuclear reactor can be reduced since basic data for synthesizing axial power distributions need not be separately measured in the start-up test of the nuclear reactor contrary to a conventional ICOPS, thereby improving the economic efficiency of the nuclear power plant, and so that overall nuclear reactor core design data can be used rather than actual measurement data in the start-up test (i.e., at the beginning of a period of nuclear fuel), thereby more accurately replicating axial power distributions of the nuclear reactor core throughout the overall period of the nuclear fuel.
摘要翻译：本发明提供使用利用相同的，其中，使用神经网络电路包括输入层到输出层中的神经网络电路和在芯保护系统（ICOPS）合成核反应堆堆芯的轴向功率分布的方法，和至少一个隐藏层，每个层被配置与至少一个节点，被连接到其它层的节点的一个层的每一个节点，节点到节点的连接被用连接权重作出向变基于学习结果，最佳构成神经网络电路的respectivement节点之间的连接权重被确定的被合成基于前通过基于施加到核电厂的核反应堆堆芯的设计各种核心的设计数据，和核反应堆堆芯的轴向输出分布的学习采 -core核反应堆的外科手术过程中通过外中子通量检测器测得的通量检测器信号，所以没有执行开始 - 所需的初始时间了核反应堆的测试可自基本数据来减少对合成轴向功率分布不需要在核反应堆相反常规ICOPS的启动测试单独测量，从而提高了核电厂的经济效率，以及所以没有整体核反应堆芯的设计数据，可以使用，而不是在启动测试实际测量数据（即，在一个周期的核燃料的开始），从而更精确地设定复制整个核反应堆堆芯的轴向输出分布核燃料的整个周期。

8. 发明公开

EP3809421A1 SPACER GRID OF NUCLEAR FUEL ASSEMBLY HAVING SIMPLE SHAPE STRUCTURE 审中-实审转让
公开(公告)号：EP3809421A1
公开(公告)日：2021-04-21
申请号：EP20167415.7
申请日：2020-03-31
申请人： Kepco Nuclear Fuel Co., Ltd
发明人： KIM, Kanghoon , YUN, Kwangho , PARK, Sangjoon , KIM, Euijae , KIM, Byeungseok , LEE, Younghwa
IPC分类号： G21C3/34 , G21C3/356
摘要： Disclosed is a spacer grid of a nuclear fuel assembly, which may be manufactured using 3D printing with a high degree of design freedom with the exclusion of sheet metal working and welding processing and may simplify the structure, improve impact strength, and reduce pressure drop. The spacer grid of a nuclear fuel assembly of the present invention includes square grid cells (110) having respective inner walls (111) and constituting a square lattice structure, wherein each of the grid cells (110) includes: a plurality of springs (120) for elastically supporting a fuel rod, each of the plurality of the springs having a fixed end (121) along a vertical direction in each of the inner walls (111) and having a free end (122) by being curvedly provided in a horizontal direction from the fixed end (121); a plurality of flow channels (130) each provided in the vertical direction to the grid cells (110) ; and a plurality of mixing vanes (140) protrudingly provided in a downstream direction of coolant flow at end parts of the grid cells (110).

9. 发明公开

EP3745418A1 NUCLEAR FUEL SINTERED BODY HAVING EXCELLENT IMPACT RESISTANCE 有权
公开(公告)号：EP3745418A1
公开(公告)日：2020-12-02
申请号：EP18901975.5
申请日：2018-07-30
申请人： Kepco Nuclear Fuel Co., Ltd
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： G21C3/04 , C04B35/10 , C04B38/06
摘要： The present invention relates to a sintered body in a cylindrical shape manufactured by UO 2 powder, the sintered body consisting of a dish (10) having both ends of a cylindrical shape formed by spherical grooves, wherein the centers of the both end surfaces have a constant curved surface; a shoulder (20) circularly formed along the rim of the dish (10) having a constant width, which is perpendicular to the cylindrical shape; and a chamfer (30) formed as a chamfered edge along the rim of the shoulder (20). Provided is a nuclear fuel sintered body having excellent impact resistance, wherein the width (SW) of the shoulder (20) is 0.20 mm to 0.80 mm and the angle between the chamfer (30) and the horizontal plane is 14° to 18°, thereby enhancing the impact strength of the sintered body as the shape of the sintered body is improved, so as to minimize the Pellet-Clad Mechanical Interaction (PCMI) damage by means of a missing pellet surface (MPS).

10. 发明公开

EP3709311A1 LOCK INSERT OF NUCLEAR FUEL ASSEMBLY UPPER FIXTURE, AND SEPARATING/COUPLING SYSTEM OF NUCLEAR FUEL ASSEMBLY UPPER FIXTURE, INCLUDING SAME 审中-公开
公开(公告)号：EP3709311A1
公开(公告)日：2020-09-16
申请号：EP17931122.0
申请日：2017-11-17
申请人： Kepco Nuclear Fuel Co., Ltd
发明人： RYU, Su Pil , KIM, Seong Soo , KIM, Ba Leum , CHUN, Joo Hong , PARK, Nam Gyu , YOO, Jong Sung
IPC分类号： G21C3/33
摘要： A lock insert of a nuclear fuel assembly upper fixture is disclosed. The present invention relates to the lock insert, which is coupled to a guide hole formed at a channel plate of the nuclear fuel assembly upper fixture so as to support the upper fixture, and includes a hollow body and an insertion part provided at the upper part of the body and inserted in the guide hole, wherein the insertion part varies in circumference size so as to be inserted into the guide hole. A separating/coupling system of the nuclear fuel assembly upper fixture, including the lock insert of the nuclear fuel assembly upper fixture, is disclosed. The present invention comprises: the upper fixture; the channel plate provided at the lower part of the upper fixture so as to allow cooling water to flow; the guide hole formed at the channel plate; the hollow lock insert including the insertion part to be inserted into the guide hole; and a separating member for separating the lock insert from the guide hole, wherein the insertion part of the lock insert varies in circumference size so as to be inserted in or separated from the guide hole. Additionally, the present invention simplifies an operation for disassembling and reassembling the nuclear fuel assembly upper fixture and the lock insert so as to make the operation convenient and reduce man-hours, thereby being effective in maintaining and repairing the nuclear fuel assembly.

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