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1. 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。

2. 发明公开

EP3495029A1 MODULAR EXTRACTION TOWER 有权
公开(公告)号：EP3495029A1
公开(公告)日：2019-06-12
申请号：EP16911721.5
申请日：2016-11-11
申请人： Kepco Nuclear Fuel Co., Ltd
发明人： BAE, Youngmoon , YANG, Seungchul , LEE, Byungkuk , KWAK, Dongyong , MIN, Junsang
IPC分类号： B01D11/04
摘要： The present invention relates to a modular extraction tower (1), as a modularized extraction tower, which is easily manufactured and provided and enables convenient maintenance and repair work, such as changing of a process or an inner structure of the extraction tower, replacing of a damaged structure, or decontaminating even after installation, and comprises: a head block (10) having a flange (110) provided on one surface thereof; a body block (20) having mounting modules (210), which are stacked on and assembled with the flange (110), have a first module flange (212) and a second module flange (213) at both sides thereof in different directions along the same axis, have an accommodation part (211) having a predetermined area and formed therein, and are coupled to each other, such that the first module flange (212) and the second module flange (213) face each other; and an inner structure provided in the accommodation part (211) and dispersing fluid, wherein the head block (10) and the body block (20) communicate with each other, and the accommodation part (211) has a square cross section, which is vertical with respect to the longitudinal direction.

3. 发明公开

EP3488909A1 DEVICE FOR CONTROLLING INTERFACE OF LIQUID-LIQUID EXTRACTION COLUMN USING PRESSURE EQUILIBRIUM 审中-公开
公开(公告)号：EP3488909A1
公开(公告)日：2019-05-29
申请号：EP16910643.2
申请日：2016-11-11
申请人： Kepco Nuclear Fuel Co., Ltd
发明人： BAE, Youngmoon , YANG, Seungchul , LEE, Byungkuk , KWAK, Dongyong , CHO, Hyunkwang
IPC分类号： B01D11/04
摘要： Disclosed is a device for controlling an interface of a liquid-liquid extraction column using pressure equilibrium. The device includes a vertical pipe provided beside an extraction column parallel thereto. The device enables internal pressures of the extraction column and the vertical pipe to be balanced with each other by moving fluid from the extraction column into the vertical pipe. Therefore, the device can maintain the level of an interface between fluids having different specific gravities with a simple control system. The device includes the liquid-liquid extraction column having a column body; and upper and lower tanks having respective inlet pipes and respective outlet pipes, wherein a pipeline is connected to the outlet pipe of the lower tank, and the internal pressures are balanced by controlling a level of the fluid in the pipeline, thereby maintaining the level of the interface.

4. 发明授权

EP3282452B1 METHOD OF ANALYZING THE SINTERED DENSITY OF URANIUM OXIDE (UOX) USING A SPECTROPHOTOMETER 有权
公开(公告)号：EP3282452B1
公开(公告)日：2019-01-09
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 , G21C21/02 , G21C17/06 , G21C19/46 , G01J3/28 , G01N21/55 , G01N9/24 , G01N21/25 , G01N33/22 , G01N33/00 , G21C3/04

5. 发明公开

EP3546427A1 LARGE-PARTICLE-SIZE AMMONIUM URANATE HYDRATE CRYSTAL, AND PREPARATION METHOD AND APPARATUS THEREFOR 审中-公开
公开(公告)号：EP3546427A1
公开(公告)日：2019-10-02
申请号：EP16922486.2
申请日：2016-12-29
申请人： Kepco Nuclear Fuel Co., Ltd
发明人： BAE, Youngmoon , YANG, Seungchul , LEE, Byungkuk , KWAK, Dongyong , CHO, Hyunkwang , GU, Sunghoi , HWANG, Euijun
IPC分类号： C01G43/00 , G21C3/46
摘要： The present invention relates to a large-particle-size ammonium uranate hydrate crystal, and a preparation method therefor. The present invention, unlike a conventional ADU process in which a uranyl nitrate aqueous solution and ammonia water are reacted, controls a reaction rate by injecting gaseous ammonia into a uranyl nitrate aqueous solution, such that the particle diameter of ammonium uranate hydrate crystals to be generated can be increased, and in the experimental result, the average particle size of finally prepared ammonium uranate hydrate crystals was 9.32-14.68 µm, which is at least 100 times greater than that of crystals prepared by the conventional ADU process. In addition, in a filtrate analysis result, the uranium content was less than 1 ppm. Since the diameter of the ammonium uranate hydrate crystals prepared according to the present invention is very large compared to those of the conventional crystals, handling in filtration, drying and roasting/reduction processes, which are subsequent processes, is much easier than in the conventional ADU process and designing apparatuses for the subsequent processes is also simpler than that of the conventional process, and since a filtrate generated in a filtration process hardly contains uranium, a separate chemical treatment process for uranium recovery is unnecessary, and thus facility investment costs can be greatly reduced.

6. 发明公开

EP3450581A1 METHOD FOR COLLECTING URANIUM BY TREATMENT PROCESS OF WASHING WASTE LIQUID GENERATED IN URANIUM HEXAFLUORIDE CYLINDER WASHING PROCESS 有权
公开(公告)号：EP3450581A1
公开(公告)日：2019-03-06
申请号：EP16900611.1
申请日：2016-11-23
申请人： Kepco Nuclear Fuel Co., Ltd
发明人： BAE, Youngmoon , SHIN, Hyundong , YANG, Seungchul , JO, Bohyun , LEE, Byungkuk , KWAK, Dongyong , CHO, Hyunkwang , GU, Sunghoi , HWANG, Euijun
IPC分类号： C22B60/02 , G21F9/08 , G21F9/10 , G21F9/12 , C02F9/00 , C02F1/58 , C02F1/52 , C02F1/04 , B01D35/02 , G01T1/167
摘要： Disclosed are a method and a device for recovering uranium (U) using a process for chemically treating washing wastewater of a uranium hexafluoride (UF 6 ) cylinder. The method and the device are provided to separate uranium (U) from the wastewater released during a process of washing the uranium hexafluoride (UF 6 ) cylinder and to release a filtrate that satisfies atomic energy licensing standards and environmental regulation standards using evaporation and condensation. Accordingly, an independent technology and process for treating the wastewater released during the process of washing the uranium hexafluoride (UF 6 ) cylinder are ensured, which provides easier maintenance and greatly reduces costs compared to the purchase and operation of apparatuses manufactured by foreign makers.

7. 发明公开

EP3275522A1 APPARATUS AND METHOD FOR SUPPLYING PULSE TO SOLVENT EXTRACTION COLUMN 审中-公开
标题翻译：将脉冲提供给溶剂萃取塔的装置和方法
公开(公告)号：EP3275522A1
公开(公告)日：2018-01-31
申请号：EP16202654.6
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
IPC分类号： B01D11/04
CPC分类号： G21F9/04 , B01D11/04 , B01D11/0438 , F04B43/04 , F04B43/06
摘要： Disclosed are an apparatus and a method for supplying a pulse to solvent extraction column (hereinafter, pulsed column). More particularly, the present invention relates to a low cost apparatus with a simple method for stably supplying a pulse to a pulsed column (10), which is employed as unit equipment in a solvent extraction process. The apparatus for supplying a pulse to the pulsed column having a first solvent inlet (52) and a second solvent outlet (58) at the low part of the pulsed column, and a second solvent inlet (56) and a first solvent outlet (54) at the top part of the pulsed column thereof, includes: a diaphragm pump (20) actuated by using electric power or compressed air, and having a discharge part (42) and a suction part (44), in which one of the discharge part and the suction part is blinded while the remaining one thereof is connected to the pulsed column via a pulse supply line (40).
摘要翻译：公开了一种向溶剂萃取塔（以下称为脉冲塔）供应脉冲的设备和方法。更具体地说，本发明涉及一种具有简单方法的低成本设备，用于向脉冲柱（10）稳定供应脉冲，脉冲柱（10）在溶剂萃取过程中用作单元设备。用于向脉冲塔供应脉冲的设备具有位于脉冲塔低部分的第一溶剂入口（52）和第二溶剂出口（58），以及第二溶剂入口（56）和第一溶剂出口（54））包括：利用电力或压缩空气驱动的隔膜泵（20），该隔膜泵具有排出部（42）和吸入部（44），其中排出部吸入部分被遮蔽，其余部分通过脉冲供给管线（40）与脉冲列连接。

8. 发明公开

EP3816602A1 SYSTEM FOR SENSING UF6 GAS LEAK IN NUCLEAR FUEL MANUFACTURING PROCESS 审中-实审
公开(公告)号：EP3816602A1
公开(公告)日：2021-05-05
申请号：EP18924411.4
申请日：2018-08-16
申请人： Kepco Nuclear Fuel Co., Ltd
发明人： BAE, Youngmoon , YANG, Seungchul , KWAK, Dongyong , LEE, Byungkuk , CHO, Hyunkwang , LEE, Junho
IPC分类号： G01M3/38 , G21C21/00 , G01M3/20
摘要： The present invention relates to a system for sensing a UF6 leak in a nuclear fuel manufacturing process and, more specifically, to a system, for sensing a UF 6 leak in a nuclear fuel manufacturing process, which senses whether or not there is a UF 6 leak by optically detecting UO 2 F 2 in a solid state generated due to a reaction with the outside air, and thus allows prevention of damage to a detection apparatus by means of sensing in a non-contact manner whether or not there is a UF 6 leak, and allows extension of mechanical life and reduction of the maintenance and repair cost for the detection apparatus.

9. 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.

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