公开(公告)号：US20160351278A1

公开(公告)日：2016-12-01

申请号：US15112578

申请日：2014-11-27

申请人： STATE ATOMIC ENERGY CORPORATION "ROSATOM" ON BEHALF OF THE RUSSIAN FEDERATION

发明人： Viktor Nikolaevich LEONOV ,  Aleksandr Viktorovich LOPATKIN ,  Elena Aleksandrovna RODINA ,  Yuriy Vasilievich CHERNOBROVKIN

IPC分类号： G21C3/04 ,  G21C3/58 ,  G21C5/14 ,  G21C1/02

CPC分类号： G21C3/04 ,  G21C1/02 ,  G21C1/022 ,  G21C3/42 ,  G21C3/58 ,  G21C5/14 ,  G21C2003/045 ,  G21Y2002/50 ,  G21Y2004/10 ,  G21Y2004/30 ,  Y02E30/34 ,  Y02E30/35 ,  Y02E30/38

摘要： An active zone includes a homogeneous uranium-plutonium nitride fuel, the mass fraction of which is a minimum 0.305, and consists of central, intermediate and peripheral parts which form fuel assemblies comprising fuel elements with geometrically identical shells but differing heights. The radial distribution of the fuel across the volume of the active zone has a stepped shape. The radius of the central part is from 0.4 to 0.5 of the effective active zone radius, while the height of the fuel column in the fuel elements in the central part is from 0.5 to 0.8 of the height of the fuel column in the peripheral part. The heights of the fuel columns forming a stepped intermediate part for diameters ranging from 0.5 to 0.85 of the effective active zone diameter are within the range from 0.55 to 0.9 of the height of the fuel column in the peripheral part.

摘要翻译： 活性区域包括均质的铀 - 钚氮化物燃料，其质量分数最小为0.305，并且由中心部分，中间部分和周边部分组成，其形成燃料组件，其包括具有几何相同壳体但不同高度的燃料元件。 燃料在活性区域的体积上的径向分布具有阶梯形状。 中心部分的半径为有效活动区域半径的0.4至0.5，而中心部分燃料元件中的燃料柱的高度为周边部分燃料柱高度的0.5至0.8。 形成直径为有效活性区域直径的0.5至0.85的阶梯式中间部分的燃料柱的高度在周边部分中的燃料柱的高度的0.55至0.9的范围内。

公开(公告)号：US20160254067A1

公开(公告)日：2016-09-01

申请号：US15084577

申请日：2016-03-30

申请人： Westinghouse Electric Company LLC

发明人： Jason P. Mazzoccoli ,  Edward J. Lahoda ,  Peng Xu

IPC分类号： G21C21/02 ,  C23C24/04 ,  C23C4/129 ,  G21C3/07 ,  C23C4/06

CPC分类号： G21C21/02 ,  C23C4/00 ,  C23C4/02 ,  C23C4/06 ,  C23C4/10 ,  C23C4/12 ,  C23C4/129 ,  C23C24/04 ,  C23C28/321 ,  C23C28/324 ,  G21C3/07 ,  G21C3/324 ,  G21Y2002/103 ,  G21Y2004/10 ,  Y02E30/40 ,  Y02T50/6765

摘要： A zirconium alloy nuclear reactor cylindrical cladding has an inner Zr substrate surface (10), an outer volume of protective material (22), and an integrated middle volume (20) of zirconium oxide, zirconium and protective material, where the protective material is applied by impaction at a velocity greater than 340 meters/second to provide the integrated middle volume (20) resulting in structural integrity for the cladding.

公开(公告)号：US08731132B2

公开(公告)日：2014-05-20

申请号：US13362962

申请日：2012-01-31

申请人： Masato Okamura ,  Tetsuo Oosato ,  Seiji Yamamoto ,  Tadasu Yotsuyanagi ,  Nagayoshi Ichikawa ,  Kenji Yamazaki ,  Junichi Takagi ,  Hidehiro Urata ,  Shunichi Suzuki ,  Kenro Takamori ,  Junichi Suzuki

发明人： Masato Okamura ,  Tetsuo Oosato ,  Seiji Yamamoto ,  Tadasu Yotsuyanagi ,  Nagayoshi Ichikawa ,  Kenji Yamazaki ,  Junichi Takagi ,  Hidehiro Urata ,  Shunichi Suzuki ,  Kenro Takamori ,  Junichi Suzuki

IPC分类号： G21C15/28

CPC分类号： G21C17/0225 ,  G21C13/08 ,  G21C17/022 ,  G21Y2002/103 ,  G21Y2004/10 ,  Y02E30/40

摘要： In a nuclear power plant, a corrosion-resistant oxide film on a surface of the metal component of a reactor structure is exposed to a high-temperature water, the corrosion-resistant oxide film containing an oxide having a property of a P-type semiconductor, and a catalytic substance having a property of an N-type semiconductor is deposited on the oxide film. The oxide film maintains the property of the P-type semiconductor.

摘要翻译： 在核电站中，将反应器结构体的金属成分表面的耐腐蚀氧化膜暴露于高温水中，含有具有P型半导体的性质的氧化物的耐腐蚀性氧化物膜 ，并且在氧化物膜上沉积具有N型半导体性质的催化物质。 氧化膜保持P型半导体的性质。

公开(公告)号：US20130272476A1

公开(公告)日：2013-10-17

申请号：US13913633

申请日：2013-06-10

申请人： AREVA NP

发明人： Bernhard Stellwag ,  Wilfried Ruehle

IPC分类号： C23F11/00

CPC分类号： C23F11/00 ,  C23F11/122 ,  G21C15/28 ,  G21C17/0225 ,  G21C19/28 ,  G21C19/307 ,  G21Y2002/103 ,  G21Y2004/10 ,  G21Y2004/303 ,  Y02E30/31

摘要： A method for protecting the components of the primary system of a boiling water reactor, especially against stress cracking corrosion, includes feeding a reducing agent into the primary coolant in order to reduce the number of substances having a oxidizing effect or in order to modify the electrochemical potential of the component surfaces covered with an oxide layer to negative values. An alcohol that can be oxidized in the conditions of a reactor is fed in as a reducing agent, preferably in a liquid form, into the primary coolant. The component surfaces are provided with a blank coating or a single intrinsic oxide coating.

摘要翻译： 用于保护沸水反应器的主要系统的组分，特别是防止应力开裂腐蚀的方法包括将还原剂进料到主冷却剂中以减少具有氧化作用的物质的数量，或为了改变电化学 被氧化物层覆盖的部件表面的电位为负值。 可以在反应器的条件下被氧化的醇作为还原剂，优选以液体形式加入到一次冷却剂中。 组件表面设置有空白涂层或单一固有氧化物涂层。

公开(公告)号：US08320515B2

公开(公告)日：2012-11-27

申请号：US12438555

申请日：2007-08-13

申请人： Lars Hallstadius ,  Mats Dahlback

发明人： Lars Hallstadius ,  Mats Dahlback

IPC分类号： G21C3/00

CPC分类号： B32B15/01 ,  C22C16/00 ,  G21C3/07 ,  G21Y2002/103 ,  G21Y2002/303 ,  G21Y2004/10 ,  G21Y2004/30 ,  G21Y2004/40 ,  Y02E30/40

摘要： A water reactor fuel cladding tube (4) is described. The tube (4) comprises an outer layer (6) of a first zirconium based alloy and has metallurgically bonded thereto an inner layer (7) of a second zirconium based alloy. The inner layer protects (7) the cladding tube (4) against stress corrosion cracking. The second zirconium based alloy comprises tin as an alloying material, and each one of the zirconium based alloys comprises at least 96 percent by weight zirconium. The first zirconium based alloy comprises at least 0.1 percent by weight niobium. A method of manufacturing the cladding tube (4) is also described and comprises the step of co-extruding two tubes of different zirconium based alloys to produce the cladding tube (4).

摘要翻译： 描述了一种水反应堆燃料包壳管（4）。 管（4）包括第一锆基合金的外层（6），并且与第二锆基合金的内层（7）冶金结合。 内层保护（7）包壳管（4）免受应力腐蚀开裂。 第二锆基合金包含锡作为合金材料，并且每种锆基合金包含至少96重量％的锆。 第一锆基合金包含至少0.1重量％的铌。 还描述了制造包壳管（4）的方法，并且包括共挤出不同锆基合金的两个管以产生包层管（4）的步骤。

公开(公告)号：US08107584B2

公开(公告)日：2012-01-31

申请号：US12149642

申请日：2008-05-06

申请人： Michael S. Defilippis ,  James P. Carneal

发明人： Michael S. Defilippis ,  James P. Carneal

IPC分类号： G21C19/00

CPC分类号： F16F9/19 ,  F16F2224/00 ,  G21D1/00 ,  G21Y2002/104 ,  G21Y2002/206 ,  G21Y2002/303 ,  G21Y2002/304 ,  G21Y2004/10 ,  G21Y2004/30 ,  Y02E30/40

摘要： Example embodiment damping devices may include a housing capturing a piston. The housing may be filled and/or able to be filled with a damping fluid compatible with the nuclear reactor coolant, so that a leak from the housing or coolant passing into the housing does not damage the reactor or example embodiment devices. Example embodiments may further include one or more springs that provide an elastic force opposing movement between the piston and housing. A shaft of the piston and an end of the housing may be connected to two nuclear reactor components with relative motion or vibration to be damped. Example methods may use example embodiment damping devices to reduce and/or prevent relative motion and vibration among components of a nuclear reactor.

摘要翻译： 示例性实施例阻尼装置可以包括捕获活塞的壳体。 壳体可以被填充和/或能够填充与核反应堆冷却剂相容的阻尼流体，使得从壳体或冷却剂通过壳体的泄漏不会损坏反应堆或示例性实施例装置。 示例性实施例可以进一步包括提供相对于活塞和壳体之间的运动的弹性力的一个或多个弹簧。 活塞的轴和壳体的端部可以连接到具有相对运动或振动的两个核反应堆部件以被阻尼。 示例性方法可以使用示例性实施例的阻尼装置来减少和/或防止核反应堆的部件之间的相对运动和振动。

公开(公告)号：US08002314B2

公开(公告)日：2011-08-23

申请号：US11577249

申请日：2005-09-26

申请人： Yves Meyzaud ,  Jean Alain Le Duff

发明人： Yves Meyzaud ,  Jean Alain Le Duff

IPC分类号： F16L41/02 ,  F16L41/00

CPC分类号： G21C17/017 ,  F16L41/021 ,  G21D1/02 ,  G21Y2002/104 ,  G21Y2002/301 ,  G21Y2004/10 ,  G21Y2004/30 ,  Y02E30/40

摘要： A T-shaped pipe fitting element comprises a main tubular branch having first and second ends for connection to first and second pipe fitting sections of an auxiliary circuit, respectively, and a lateral branch having an axis which is at an angle to the axis of the main branch, and a free end for connecting to a third pipe fitting section of the auxiliary circuit. The first, second, and third pipe fitting sections each have different functions. One supplies the pipe fitting element with a first fluid at a high temperature, another supplies a second fluid to the pipe fitting element, at a lower temperature than the first fluid, and the third discharges a mixture of the first and second fluids. The pipe fitting sections consist of austenitic stainless steel. The T-shaped pipe fitting consists of stainless martensitic steel with improved thermal endurance properties.

摘要翻译： T型管接头元件包括主管状分支，其具有第一和第二端，用于分别连接到辅助回路的第一和第二配管部分，以及横向分支，该轴线具有与轴线成一定角度的轴线 主分支和用于连接到辅助电路的第三管配件部分的自由端。 第一，第二和第三管道配件部分各自具有不同的功能。 一个在高温下为第一流体供应管接头元件，另一个在比第一流体低的温度下将第二流体供应到管接头元件，而第三流体排出第一和第二流体的混合物。 管接头部分由奥氏体不锈钢组成。 T型管件由不锈钢马氏体钢组成，具有改善的耐热性能。

公开(公告)号：US20110108746A1

公开(公告)日：2011-05-12

申请号：US12999352

申请日：2009-06-16

申请人： Jacques Bara ,  Daniel Mottier

发明人： Jacques Bara ,  Daniel Mottier

IPC分类号： G21F5/10 ,  G21F5/12

CPC分类号： G21C19/06 ,  G21F5/012 ,  G21F5/10 ,  G21Y2002/10 ,  G21Y2002/302 ,  G21Y2002/304 ,  G21Y2002/60 ,  G21Y2004/10 ,  G21Y2004/30

摘要： The subject of the present invention is: a casing internal part (1) suitable for the dry intermediate storage of at least one irradiated fuel element. Said casing internal part (1) has a tiered structure which comprises at least two superposed modules (M1, M2, M3, M4), each of said modules (M1, M2, M3, M4), made of a material that is a good conductor of heat, with compartment(s) (2a, 2b) for accommodating said fuel element(s) in the central part and with at least one hollowed-out peripheral heat sink (3a, 3b), being arranged on a support plate (4) that is perforated to allow said fuel element(s) through; the perforated support plates (4) of said structure being positioned and assembled by means of a retaining system (5′+5+5″), with a clearance (J) left between the top of the module of one tier (Mi) and the perforated support plate (4) of the tier (Mi+1) immediately above; a temporary storage casing (10) equipped with such a casing internal part (1); and the corresponding temporary storage method.

摘要翻译： 本发明的主题是：适用于至少一个辐射燃料元件的干中间储存的壳体内部部分（1）。 所述壳体内部部件（1）具有分层结构，其包括至少两个叠置的模块（M1，M2，M3，M4），每个所述模块（M1，M2，M3，M4）由材料制成 具有用于将所述燃料元件容纳在中心部分中的隔室（2a，2b）和至少一个中空的周边散热器（3a，3b），其布置在支撑板上（ 4），其被穿孔以允许所述燃料元件通过; 所述结构的穿孔支撑板（4）通过保持系统（5'+ 5 + 5“）定位和组装，间隙（J）留在一层（Mi）的模块的顶部和 紧靠上方的层（Mi + 1）的穿孔支撑板（4） 装备有这种壳体内部部件（1）的临时存储壳体（10）; 和相应的临时存储方法。

公开(公告)号：US07813463B2

公开(公告)日：2010-10-12

申请号：US09996244

申请日：2001-11-28

申请人： Daniel Richard Schaefer ,  James Michael Snead

发明人： Daniel Richard Schaefer ,  James Michael Snead

IPC分类号： G21B1/00

CPC分类号： B82Y30/00 ,  G21F1/10 ,  G21F5/015 ,  G21Y2002/10 ,  G21Y2004/10

摘要： A fullerene molecule having one or more free thermal neutrons trapped within the fullerene molecule and a method for trapping and storing neutrons within a fullerene molecule are described.

摘要翻译： 描述了具有一个或多个俘获在富勒烯分子内的游离热中子的富勒烯分子以及在富勒烯分子内捕获和储存中子的方法。

公开(公告)号：US07738620B2

公开(公告)日：2010-06-15

申请号：US11659656

申请日：2005-07-19

申请人： Pierre Barberis ,  Jean-Paul Mardon ,  Véronique Rebeyrolle ,  Jean-Luc Aubin

发明人： Pierre Barberis ,  Jean-Paul Mardon ,  Véronique Rebeyrolle ,  Jean-Luc Aubin

IPC分类号： G21C3/00

CPC分类号： C22C16/00 ,  G21C3/07 ,  G21C21/00 ,  G21Y2002/103 ,  G21Y2004/10 ,  G21Y2004/20 ,  G21Y2004/40 ,  Y02E30/40

摘要： A method for production of a fuel cladding tube for a nuclear reactor, characterized by the preparation of an ingot of an alloy of zirconium with the following composition by weight %: 0.8%≦Nb≦2.8%, traces≦Sn≦0.65%, 0.015%≦Fe≦0.40%, C≦100 ppm, 600 ppm≦O≦2300 ppm, 5 ppm≦S≦100 ppm, Cr+V≦0.25%, Hf≦75 ppm and F≦1 ppm the remainder being zirconium and impurities arising from production. The ingot is then subjected to forging, a hardening and thermomoechanical treatments comprising cold laminations separated by intermediate annealing, all intermediate annealings being carried out at a temperature below the α→α+β transition temperature of the alloy, finishing with a recrystallization annealing and resulting in the production of a tube, whereupon an optional external cleaning of the tube is carried out and a mechanical polishing of the external surface of the tube is carried out to give a roughness Ra less than or equal to 0.5 μm. The invention further relates to a fuel cladding tube obtained thereby.

摘要翻译： 一种生产用于核反应堆的燃料包层管的方法，其特征在于制备具有以下组成的锆的合金锭：0.8％＆lt; NlE; Nb＆nlE; 2.8％，痕量Sn; nnE; 0.65％ 0.015％＆nlE; Fe＆nlE; 0.40％，C＆lt; lE; 100ppm，600ppm＆amp; NlE; O＆amp; NEE; 2300ppm，5ppm和nlE; S＆amp; NlE; 100ppm，Cr + V和NlE; 0.25％，Hf和nEE; 75ppm和F＆ 和生产中产生的杂质。 然后对锭进行锻造，硬化和热机械处理，包括通过中间退火分离的冷层压，所有中间退火在低于α→α+和bgr的温度下进行; 合金的转变温度，用再结晶退火进行精加工，从而制造管，由此执行管的可选的外部清洁，并且进行管的外表面的机械抛光以得到粗糙度Ra 小于或等于0.5μm。 本发明还涉及由此获得的燃料包壳管。