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11. 发明申请

US20180356021A1 CROSS-OVER FLUID COUPLING 审中-公开
公开(公告)号：US20180356021A1
公开(公告)日：2018-12-13
申请号：US15735374
申请日：2016-06-22
申请人： ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE
发明人： James M. King , Andrew B. Kittmer , Terry J. Schaubel
IPC分类号： F16L39/00 , G21C21/00 , F16L59/065 , F16L37/088
CPC分类号： F16L39/005 , F16L9/19 , F16L9/20 , F16L23/12 , F16L37/088 , F16L59/065 , F28D7/106 , F28F9/26 , F28F13/06 , F28F2250/04 , F28F2250/10 , G21C1/20 , G21C3/322 , G21C3/328 , G21C15/02 , G21C21/00
摘要： A cross-over fluid coupling includes a first coupling end and a second coupling end. A plurality of first conduits have inner ends disposed toward the first coupling end and outer ends spaced apart from the inner end toward the second coupling end and being outboard of the inner end. A plurality of second conduits have outer ends that are disposed toward the first coupling end and positioned laterally outboard of the inner end of at least one of the first conduits, and inner ends that are spaced apart from the outer end toward the second coupling end in the axial direction and is laterally inboard of the outer end of the at least one of the first conduits.

12. 发明授权

US10119181B2 Treatment process for a zirconium alloy, zirconium alloy resulting from this process and parts of nuclear reactors made of this alloy 有权
公开(公告)号：US10119181B2
公开(公告)日：2018-11-06
申请号：US14759791
申请日：2013-01-11
申请人： AREVA NP
发明人： Pierre Barberis , Pascal Guerin , Pascaline Fremiot
IPC分类号： C22C16/00 , C22F1/18 , G21C3/07 , G21C3/30 , G21C21/00
摘要： A treatment process for a zirconium alloy is provided. The process includes the following steps: a zirconium alloy ingot is prepared, the composition of which is: 0.40%≤Nb≤1.05%; traces≤Sn≤2%; (0.5Nb−0.25) %≤Fe≤0.50%; traces≤Ni≤0.10%; traces≤(Cr+V) %≤0.50%; traces≤S≤35 ppm; 600 ppm≤O≤2000 ppm, preferably 1200 ppm≤O≤1600 ppm; traces≤Si≤120 ppm; traces≤C≤150 ppm; the remaining being Zr and unavoidable impurities; the ingot undergoes at least one reheating and hot shaping step, and possibly a reheating and quenching step following a hot shaping step; optionally the hot-shaped ingot undergoes an annealing; the hot-shaped and possibly annealed ingot undergoes at least one cycle of cold rolling-annealing steps; the annealing of at least one of the cold rolling-annealing steps being performed at a temperature comprised between 600° C. and the lowest of either 700° C. or (710−20×Nb %)° C., and the annealings of the other cold rolling-annealing steps, if any, being performed at a temperature not higher than 600° C. Also provided are a Zr alloy so obtained, and part of a fuel assembly for a light water nuclear reactor made of it.

13. 发明授权

US10020077B2 Pressurized water reactor with upper vessel section providing both pressure and flow control 有权
公开(公告)号：US10020077B2
公开(公告)日：2018-07-10
申请号：US14673087
申请日：2015-03-30
申请人： BWXT mPower, Inc.
发明人： Scott J. Shargots
IPC分类号： G21C1/32 , G21C1/09 , G21C15/243 , G21C1/08 , F04D13/10 , G21C15/24 , G21C21/00 , G21D1/04
CPC分类号： G21C1/32 , F04D13/10 , G21C1/086 , G21C1/09 , G21C15/24 , G21C15/243 , G21C21/00 , G21D1/04 , Y02E30/32 , Y10T29/49236 , Y10T29/49245
摘要： A pressurized water reactor (PWR) includes a vertical cylindrical pressure vessel having a lower portion containing a nuclear reactor core and a vessel head defining an integral pressurizer. A reactor coolant pump (RCP) mounted on the vessel head includes an impeller inside the pressure vessel, a pump motor outside the pressure vessel, and a vertical drive shaft connecting the motor and impeller. The drive shaft does not pass through the integral pressurizer. The drive shaft passes through a vessel penetration of the pressure vessel that is at least large enough for the impeller to pass through.

14. 发明申请

US20180047466A1 FUEL CHANNEL FOR A NUCLEAR BOILING WATER REACTOR 审中-公开
公开(公告)号：US20180047466A1
公开(公告)日：2018-02-15
申请号：US15555832
申请日：2015-03-13
申请人： Westinghouse Electric Sweden AB
发明人： Anders Söderlund , Markus Månsson
IPC分类号： G21C3/324 , G21C21/00
摘要： A method of making a fuel channel for a fuel assembly for a nuclear power boiling water reactor includes providing at least one first sheet of a Zr-based material of a first thickness, providing at least one second sheet of a Zr-based material of a second thickness, which is less than said first thickness, assembling at least said at least one first sheet and said at least one second sheet, such that a fuel channel is formed and such that said at least one first sheet forms a lower part of the fuel channel and such that said at least one second sheet forms a higher part of the fuel channel and such that said lower part is joined with said higher part, wherein said lower part constitutes 20-75% of the length of the fuel channel. The invention also concerns a fuel channel and a fuel assembly.

15. 发明授权

US09862047B2 Welding method and steam generator channel head 有权
公开(公告)号：US09862047B2
公开(公告)日：2018-01-09
申请号：US14372414
申请日：2012-11-28
申请人： MITSUBISHI HEAVY INDUSTRIES, LTD.
发明人： Takashi Hanioka , Hirokazu Kadowaki , Taisuke Ito
IPC分类号： B23K9/04 , F22B37/00 , G21C21/00 , G21D1/00 , B23K9/18 , B23K25/00 , F22B1/02
CPC分类号： B23K9/044 , B23K9/046 , B23K9/048 , B23K9/18 , B23K9/186 , B23K25/005 , F22B1/025 , F22B37/002 , G21C21/00 , G21D1/006 , Y02E30/40
摘要： A welding method for making cladding or buttering on an inner surface of a base material, an inner surface of an opening portion formed in the base material, and the cut surface formed in such a manner that the cut surface is continuous from the inner surface of the base material to the inner surface of the opening portion, wherein the welding method includes a step of forming a protruding portion on the base material in advance, the protruding portion including a temporary welding surface extending toward the center of the opening portion in such a manner that the temporary welding surface is uniformly continuous to the inner surface of the base material and including the cut surface buried therein.

16. 发明申请

US20170320162A1 ELECTRIC MELTING METHOD FOR FORMING CYLINDER OF PRESSURE VESSEL OF NUCLEAR POWER STATION 审中-公开
公开(公告)号：US20170320162A1
公开(公告)日：2017-11-09
申请号：US15524617
申请日：2015-11-03
申请人： NANFANG ADDITIVE MANUFACTURING TECHNOLOGY CO., LTD.
发明人： Huaming Wang
IPC分类号： B23K25/00 , G21C13/087 , G21C21/00 , B23K101/12 , B23K103/04
CPC分类号： B23K25/005 , B22F3/1055 , B22F5/106 , B22F2003/1056 , B22F2999/00 , B23K9/04 , B23K9/18 , B23K9/298 , B23K2101/12 , B23K2103/04 , B23K2103/05 , B33Y10/00 , B33Y80/00 , G21C13/087 , G21C21/00 , Y02P10/295 , B22F2202/06 , B22F3/115 , B22F7/08 , B22F2003/247
摘要： An electric melting method for forming a cylinder of a pressure vessel of nuclear power station, in which an electric melting head and a base material are connected to the anode and cathode of a power supply respectively. During the forming of a metal component, the raw metal wire is sent to a surface of the base material by a feeder and the electric melting head to create the electric arc between the raw wire and the base material, wherein the electric arc melts certain of deposited auxiliary material and crates a molten slag pool; a current creates the resistance heat and the electroslag heat; the raw wire is molten under the high-energy heat resource composed of the electric arc heat, the resistance heat and the electroslag heat, and creates a molten pool on partial surface of the base material.

17. 发明授权

US09745642B2 Method for heat treating a metal tube or pipe, metal tube or pipe, and heat treatment furnace 有权
公开(公告)号：US09745642B2
公开(公告)日：2017-08-29
申请号：US14385830
申请日：2013-03-08
申请人： NIPPON STEEL & SUMITOMO METAL CORPORATION
发明人： Osamu Miyahara , Toshihiro Imoto
IPC分类号： F27D5/00 , C21D9/08 , C22C19/05 , C22C38/58 , C22F1/00 , C22F1/10 , C21D8/10 , C22C38/00 , C22C38/02 , C22C38/06 , C22C38/42 , C22C38/50 , F22B37/00 , C21D9/00 , C22C30/00 , C22C30/02 , C22C38/04 , F16L9/02 , C22C38/40 , C21D1/773 , C21D1/00 , G21D1/00 , G21C21/00
CPC分类号： C21D9/08 , C21D1/00 , C21D1/773 , C21D8/10 , C21D8/105 , C21D9/0025 , C22C19/05 , C22C19/053 , C22C19/055 , C22C19/056 , C22C19/058 , C22C30/00 , C22C30/02 , C22C38/001 , C22C38/002 , C22C38/02 , C22C38/04 , C22C38/06 , C22C38/40 , C22C38/42 , C22C38/50 , C22C38/58 , C22F1/00 , C22F1/10 , F16L9/02 , F22B37/007 , G21C21/00 , G21D1/00
摘要： A method for heat treating a metal tube or pipe is provided to perform heat treatment in such a manner that metal tubes or pipes (1) to be accommodated in a heat treatment furnace are laid down on a plurality of cross beams (22) arranged along a longitudinal direction of the metal tubes or pipes with the distance between adjacent cross beams being in a range of 200 to 2500 mm. This makes it possible to inhibit bending and scratches of the metal tubes or pipes without causing discoloration and deterioration of the manufacturing efficiency for the metal tubes or pipes. When the metal tubes or pipes (1) are laid down on the cross beams (22), spacers may be interposed between the metal tubes or pipes (1) and the cross beams (22) on which they are laid down.

18. 发明授权

US09646728B2 Plasma welding apparatus for guide thimble and guide thimble end plug of nuclear fuel assembly 有权
公开(公告)号：US09646728B2
公开(公告)日：2017-05-09
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： B23K10/00 , G21C21/00 , B23K10/02 , B23K37/02 , G21C3/334
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).

19. 发明授权

US09303298B2 Porous UO2 sintered pellet for electroreduction process, and preparation method thereof 有权
标题翻译：用于电解还原工艺的多孔UO2烧结球团及其制备方法
公开(公告)号：US09303298B2
公开(公告)日：2016-04-05
申请号：US13865786
申请日：2013-04-18
申请人： KOREA ATOMIC ENERGY RESEARCH INSTITUTE
发明人： Sang-Ho Na , Dae-Yong Song , Ki Hong Kim , Sang-Oh Bae , Jong-Man Park , Chul Goo Ji , Hyong Jin Hwang
IPC分类号： G21C21/00 , C22B60/02 , C01G43/025 , G21C3/62 , C01G43/01
CPC分类号： C22B60/0208 , C01G43/01 , C01G43/025 , C01P2004/61 , C01P2006/12 , G21C3/623 , G21C21/00 , Y02E30/38 , Y10T428/2982
摘要： Porous UO2 sintered pellets to be fed into an electrolytic reduction process for the purpose of metallic nuclear fuel recovery, include one or more hollow spaces formed from the surfaces toward the interiors thereof. When the porous UO2 sintered pellets are used in the electrolytic reduction process, the efficiency increases.
摘要翻译：用于金属核燃料回收的电解还原方法的多孔UO2烧结颗粒包括从表面向其内部形成的一个或多个中空空间。当在电解还原过程中使用多孔UO2烧结颗粒时，效率提高。

20. 发明申请

US20150354030A1 TREATMENT PROCESS FOR A ZIRCONIUM ALLOY, ZIRCONIUM ALLOY RESULTING FROM THIS PROCESS AND PARTS OF NUCLEAR REACTORS MADE OF THIS ALLOY 审中-公开
标题翻译：本方法生产的锆合金，锆合金的处理工艺及本合金的核反应堆零件
公开(公告)号：US20150354030A1
公开(公告)日：2015-12-10
申请号：US14759791
申请日：2013-01-11
申请人： AREVA NP
发明人： Pierre BARBERIS , Pascal GUERIN , Pascaline FREMIOT
IPC分类号： C22C16/00 , G21C21/00 , G21C3/30 , C22F1/18 , G21C3/07
CPC分类号： C22C16/00 , C22F1/186 , G21C3/07 , G21C3/30 , G21C21/00 , Y02E30/40
摘要： A treatment process for a zirconium alloy is provided. The process includes the following steps: a zirconium alloy ingot is prepared, the composition of which is: 0.40%≦Nb≦1.05%; traces≦Sn≦2%; (0.5Nb−0.25)%≦Fe≦0.50%; traces≦Ni≦0.10%; traces≦(Cr+V)%≦0.50%; traces≦S≦35 ppm; 600 ppm≦O≦2000 ppm, preferably 1200 ppm≦O≦1600 ppm; traces≦Si≦120 ppm; traces≦C≦150 ppm; the remaining being Zr and unavoidable impurities; the ingot undergoes at least one reheating and hot shaping step, and possibly a reheating and quenching step following a hot shaping step; optionally the hot-shaped ingot undergoes an annealing; the hot-shaped and possibly annealed ingot undergoes at least one cycle of cold rolling-annealing steps; the annealing of at least one of the cold rolling-annealing steps being performed at a temperature comprised between 600° C. and the lowest of either 700° C. or (710−20×Nb %)° C., and the annealings of the other cold rolling-annealing steps, if any, being performed at a temperature not higher than 600° C. Also provided are a Zr alloy so obtained, and part of a fuel assembly for a light water nuclear reactor made of it.
摘要翻译：提供了一种锆合金的处理方法。该方法包括以下步骤：制备锆合金锭，其组成为：0.40％＆nlE; Nb＆nlE; 1.05％; trace＆nlE; Sn＆nlE; 2％; （0.5Nb-0.25）％＆nlE; Fe＆nlE; 0.50％; 痕量＆nlE; Ni＆nlE; 0.10％; 痕量＆nlE;（Cr + V）％＆nlE; 0.50％; trace＆nlE; S＆nlE; 35 ppm; 600ppm＆amp; NlE; O＆NlE; 2000ppm，优选1200ppm＆amp; NlE; O＆amp; NE; 1600ppm; 痕量和nlE; Si＆nlE; 120ppm; trace＆nlE; C＆nlE; 150 ppm; 剩余的是Zr和不可避免的杂质; 锭经历至少一个再加热和热成形步骤，并且可能在热成型步骤之后进行再加热和淬火步骤; 任选地，热形锭经历退火; 热的和可能退火的锭经历至少一个循环的冷轧退火步骤; 至少一个冷轧退火步骤的退火是在600℃至700℃或（710-20×Nb％）℃之间的最低温度下进行的，以及在不高于600℃的温度下进行其它的冷轧退火工序（如果有的话）。还提供了如此获得的Zr合金和由其制成的轻水核反应堆的燃料组件的一部分。

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