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1. 发明申请

US20220084700A1 CONTROL METHOD FOR VOLUME FRACTION OF MULTISTRUCTURAL ISOTROPIC FUEL PARTICLES IN FULLY CERAMIC MICROENCAPSULATED NUCLEAR FUELS, COMPOSITIONS FOR COATING AND SINTERED BODY OF THE SAME 有权
公开(公告)号：US20220084700A1
公开(公告)日：2022-03-17
申请号：US17082001
申请日：2020-10-27
申请人： University of seoul Industry Cooperation Foundation. , KEPCO NUCLEAR FUEL CO.,LTD
发明人： Young Wook KIM , Eun Seo KANG , Seung Jae LEE , Kwang Young LIM
IPC分类号： G21C3/62 , C04B35/565 , G21C3/20
摘要： Provided herein is a control method for volume fraction of multistructural isotropic fuel particles in a fully ceramic microencapsulated nuclear fuel including: preparing a mixture of silicon carbide, sintering additives, and organic binders, producing a coating body by coating multistructural isotropic fuel particles by using the prepared mixture, forming the coating body, and performing pressureless sintering on the formed coating body, wherein volume fraction of multistructural isotropic nuclear fuel particles may be controlled by controlling the coating layer thickness on multistructural isotropic nuclear fuel particles, wherein the coating layer was configured with a mixture of silicon carbide, sintering additives, and organic binders. As described above, stability and tolerance against nuclear fuel related accidents may be significantly enhanced, and advantageous effects of enabling a pressureless sintering procedure to be performed while maximizing volume fraction of the multistructural isotropic fuel particles may be expected.

2. 发明申请

US20210304908A1 METHOD FOR PROCESS FOR PRODUCING FULLY CERAMIC MICROENCAPSULATED FUELS CONTAINING TRISTRUCTURAL-ISOTROPIC PARTICLES WITH A COATING LAYER HAVING HIGHER SHRINKAGE THAN MATRIX 有权
公开(公告)号：US20210304908A1
公开(公告)日：2021-09-30
申请号：US17216678
申请日：2021-03-30
申请人： UNIVERSITY OF SEOUL INDUSTRY COOPERATION FOUNDATION , KEPCO NUCLEAR FUEL CO., LTD.
发明人： Young Wook KIM , Jung Hye EOM , Yu Kwang SEO , Seung Jae LEE
IPC分类号： G21C3/62 , C04B35/628 , C04B35/626 , C04B35/634 , C04B35/565 , C04B35/632 , C04B35/645 , C04B38/00 , G21C3/20 , G21C21/04
摘要： The present invention relates to a method for preparing a fully ceramic capsulated nuclear fuel material containing three-layer-structured isotropic nuclear fuel particles coated with a ceramic having a composition which has a higher shrinkage than a matrix in order to prevent cracking of ceramic nuclear fuel, wherein the three-layer-structured nuclear fuel particles before coating is included in the range of between 5 and 40 fractions by volume based on after sintering. More specifically, the present invention provides a composition for preparing a fully ceramic capsulated nuclear fuel containing three-layer-structured isotropic particles coated with the substance which includes, as a main ingredient, a silicon carbine derived from a precursor of the silicon carbide wherein a condition of ΔLc>ΔLm at normal pressure sintering is created, where the sintering shrinkage of the coating layer of the three-layer-structured isotropic nuclear fuel particles is ΔLc and the sintering shrinkage of the silicon carbide matrix is ΔLm; material produced therefrom; and a method for manufacturing the material. The residual porosity of the fully ceramic capsulated nuclear fuel material is 4% or less.

3. 发明申请

US20210050120A1 NUCLEAR FUEL PELLET HAVING EXCELLENT COMPRESSION RESISTANCE AND REDUCED SURFACE DEFECT 有权
公开(公告)号：US20210050120A1
公开(公告)日：2021-02-18
申请号：US16963281
申请日：2018-07-30
申请人： KEPCO NUCLEAR FUEL CO., LTD.
发明人： Min Young Choi , Yeon-soo Na , Kwang-young Lim , Tae Sik Jung , Seung-jae Lee , Yong Kyoon Mok , Jong Sung Yoo
IPC分类号： G21C3/04 , G21C3/06
摘要： Provided is a nuclear fuel pellet having excellent compression resistance and a reduced missing pellet surface, the pellet being a cylindrical shape and including, on each of a top surface and a bottom surface thereof: a dish configured as a spherical groove shape having a predetermined curved surface at a center; a land configured as a horizontal annular shape along a rim of the dish; and a chamfer configured as a shape in which a corner is chamfered at a predetermined angle along a rim of the land, wherein the chamfer includes: a primary chamfer adjacent to the rim of the land; and a secondary chamfer configured as a shape additionally chamfered along a rim of the primary chamfer.

4. 发明申请

US20200211723A1 MOBILE EQUIPMENT FOR MEASURING STRUCTURAL DEFORMATION OF NUCLEAR FUEL ASSEMBLY 审中-公开
公开(公告)号：US20200211723A1
公开(公告)日：2020-07-02
申请号：US16633800
申请日：2017-09-29
申请人： KEPCO NUCLEAR FUEL CO., LTD.
发明人： Mun Seog Baik , Gi Bong Kil , Kyung Hun Chang
IPC分类号： G21C17/06 , G01B11/16
摘要： Provided is mobile equipment for measuring structural deformation of a nuclear fuel assembly, the mobile equipment including: a container; a power means and a loading table disposed inside the container; a pedestal disposed on one side of the loading table of the container, the pedestal being provided with a hinge means and a fixing means configured to fix the nuclear fuel assembly upright; a column seated on the loading table and provided at one end part thereof with a rotating shaft detachably installed to the hinge means, and configured to be erected upright on the fixing means of the pedestal by power of the power means; and a scanner configured to move upward and downward in a longitudinal direction of the column and to measure the structural deformation of the nuclear fuel assembly.

5. 发明授权

US09916907B2 Combination of top nozzle and guide thimble for nuclear fuel assembly 有权
公开(公告)号：US09916907B2
公开(公告)日：2018-03-13
申请号：US15293431
申请日：2016-10-14
申请人： KEPCO NUCLEAR FUEL CO., LTD.
发明人： Nam-Gyu Park , Kyu-Tae Kim , Jung-Min Suh , Shin-Ho Lee , Kyong-Bo Eom , Joon-Kyoo Park , Jin-Sun Kim , Gyu-Cheol Shin , Seong-Ki Lee , Il-Kyu Kim , Ki-Sung Choi , Kyeong-Lak Jeon
IPC分类号： G21C3/33 , G21C3/334
CPC分类号： G21C3/3315 , G21C3/33 , G21C3/334 , G21Y2002/402 , Y02E30/40
摘要： A combination of a top nozzle and a guide thimble of a nuclear fuel assembly and, more particularly, a structure for joining an inner-extension tube, the top nozzle and the guide thimble. When an inner-extension tube head, which is provided as a means for facilitating removal of the top nozzle of the nuclear fuel assembly from the guide thimble, is removed from an inner-extension tube body to separate the top nozzle from the nuclear fuel assembly, the inner-extension tube body is prevented from undesirably rotating, so that the guide thimble and the inner-extension tube body can maintain the joined state.

6. 发明申请

US20180045703A1 METHOD OF ANALYZING SINTERED DENSITY OF URANIUM OXIDE (UOX) USING SPECTROPHOTOMETER 有权
公开(公告)号：US20180045703A1
公开(公告)日：2018-02-15
申请号：US15336996
申请日：2016-10-28
申请人： KEPCO NUCLEAR FUEL CO., LTD.
发明人： Youngmoon BAE , Seungchul YANG , Byungkuk LEE , Dongyong KWAK , Hyunkwang CHO , Sunghoi GU , Euijun HWANG
IPC分类号： G01N33/22 , G21C3/26 , G21C17/06 , G01N9/24 , G01N21/31
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
摘要： Disclosed is a method of predicting, calculating, or analyzing the sintered density of uranium oxide (UOx) 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 (UOx), which overcomes the problem with a conventional technology where the sintered density of uranium oxide (UOx) can be analyzed only in a pellet state and a subsequent treatment process needs to be performed according to the analysis result.

7. 发明申请

US20170294243A1 FUEL PELLET VISUAL INSPECTION DEVICE FOR MANUFACTURING NUCLEAR FUEL ROD 审中-公开
公开(公告)号：US20170294243A1
公开(公告)日：2017-10-12
申请号：US15280218
申请日：2016-09-29
申请人： KEPCO NUCLEAR FUEL CO., LTD.
发明人： Tae Hyung NA , Hankyul KOH
IPC分类号： G21C21/02 , G01N21/01 , G01N21/88
CPC分类号： G21C21/02 , G01B11/02 , G01N21/01 , G01N21/8803 , G01N21/94 , G01N21/952
摘要： A fuel pellet visual inspection device for manufacturing a nuclear fuel rod improves convenience and workability of visual inspection of a plurality of pellets by simultaneously turning over the pellet. The fuel pellet visual inspection device for manufacturing a nuclear fuel rod includes: a rotary shaft; a pair of seats hinged to the hinge shaft, arranged at both sides from the rotary shaft, and seated with a tray thereon; and a dust-collecting unit disposed under the pair of seats and collecting dust scattered from pellets.

8. 发明授权

US09724739B2 Gap control device for pilger die assembly of cold pilger mills 有权
公开(公告)号：US09724739B2
公开(公告)日：2017-08-08
申请号：US14526588
申请日：2014-10-29
申请人： KEPCO NUCLEAR FUEL CO., LTD.
发明人： Jung Cheol Shin , In Kyu Kim , Ki Bum Park , Yong Shin Choi , Ho Yeon Hwang
IPC分类号： B21B31/30 , B21B31/16 , B21B21/02 , B21B21/00
CPC分类号： B21B21/02 , B21B21/005 , B21B31/16 , B21B31/30
摘要： A gap control device for a Pilger die assembly of cold Pilger mills. The gap control device can independently control the height of a pair of bearing blocks which axially support an upper die. A lower plate has first and second receiving holes which respectively correspond to the upper portions of a pair of bearing blocks. First and second wedge plates are fitted into the receiving holes, and respectively have inclined surfaces on the upper portions thereof. First and second adjustment blocks respectively have inclined guide surfaces to be in surface contact with the inclined surfaces of the wedge plates, and are movable horizontally with respect to the lower plate. An upper plate is assembled to the upper portion of the lower plate to cover the adjustment blocks. First and second adjustment bolts allow the first and second adjustment blocks to be respectively manipulated in a horizontal direction.

9. 发明授权

US09196386B2 Spacer grid for nuclear fuel assembly for reducing high frequency vibration 有权
标题翻译：用于降低高频振动的核燃料组件的间隔栅格
公开(公告)号：US09196386B2
公开(公告)日：2015-11-24
申请号：US13648322
申请日：2012-10-10
申请人： KEPCO NUCLEAR FUEL CO., LTD.
发明人： Sang Youn Jeon , Jung Min Suh , Kyong Bo Eom , Joon Kyoo Park , Dong Geun Ha , Jin Sun Kim , Seong Soo Kim , Joo Young Ryu , Oh Joon Kwon
IPC分类号： G21C3/356 , G21C3/322 , G21C3/34
CPC分类号： G21C3/356 , G21C3/322 , G21C3/352 , G21C3/3563 , G21C2003/3432 , Y02E30/38
摘要： Disclosed herein is a spacer grid for a nuclear fuel assembly which is formed from grid strips of an improved structure, thus reducing flow-induced high-frequency vibration. The spacer grid has dimples or grid springs for supporting fuel rods and is formed from a plurality of grid strips assembled in a lattice shape to form lattice cells. Each of the grid strips has at least one slot formed in a planar portion of the grid strip separately from the dimple or grid spring. Therefore, characteristics of the vibration of the spacer grid can be set in a variety of different manners so that flow-induced high-frequency vibration can be reduced.
摘要翻译：本文公开了一种用于核燃料组件的间隔栅格，其由改进结构的栅格条形成，从而减少流动引起的高频振动。间隔栅格具有用于支撑燃料棒的凹坑或栅格弹簧，并且由多个栅格条形成，栅格条以格子形状形成以形成晶格单元。每个格栅条具有至少一个槽，其形成在格栅条的平面部分中，与凹坑或格栅弹簧分开形成。因此，可以以各种不同的方式设置间隔栅格的振动特性，从而可以降低流动的高频振动。

10. 发明申请

US20140190945A1 PLASMA WELDING APPARATUS FOR GUIDE THIMBLE AND GUIDE THIMBLE END PLUG OF NUCLEAR FUEL ASSEMBLY 有权
标题翻译：等离子焊接设备，用于指导导线芯和指导核燃料燃料组件的末端插头
公开(公告)号：US20140190945A1
公开(公告)日：2014-07-10
申请号：US14149102
申请日：2014-01-07
申请人： KEPCO NUCLEAR FUEL CO., LTD.
发明人： Ju Young LEE , Chang Hwan Hwang , Hung Soon Chang , Soon Ki Guk , Tae Hyung Na , Yeong Seon Oh
IPC分类号： G21C21/00 , B23K10/02
CPC分类号： G21C21/00 , B23K10/006 , B23K10/02 , B23K37/0211 , G21C3/334 , Y02E30/40
摘要： Disclosed is a plasma welding apparatus for a guide thimble and guide thimble end plug of a nuclear fuel assembly, which includes: a welding chamber (100) includes an end-plug inserting part (110) into which the end plug (10) is inserted, a guide-thimble inserting part (120) which is provided on the same axis as the end-plug inserting part (110) and into which the guide thimble (20) is inserted and fixed, a torch assembling part (130) to which a plasma welding torch (131) is assembled so as to make a right angle with the end-plug inserting part (110) and the guide-thimble inserting part (120), and argon inflow and outflow ports (141, 142) through which argon is supplied or discharged; an end-plug transfer unit (210) supplying the end plug (10) to the end-plug inserting part (110); and an guide-thimble transfer unit (220) transferring the guide thimble (20) to the guide-thimble inserting part (120).
摘要翻译：公开了一种用于核燃料组件的导向套管和导向套管端塞的等离子体焊接装置，其包括：焊接室（100），包括端塞插入部分（110），端塞（10）插入其中，引导套管插入部分（120），其设置在与所述端塞插入部分（110）相同的轴线上并且所述引导套管（20）被插入和固定到所述引导套管插入部分中;焊枪组装部分，等离子焊枪（131）组装成与端塞插入部分（110）和引导套筒插入部分（120）成直角，以及氩流入和流出端口（141,142），通过该等离子焊枪供应或排放氩气; 将端塞（10）供给到端塞插入部（110）的端塞传送单元（210）; 以及将导向套管（20）传送到导向套管插入部（120）的引导套管传送单元（220）。

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