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101.发明授权Method for the manufacture of tubes of a zirconium based alloy for nuclear reactors and their usage 失效制造用于核反应堆的锆基合金管的方法及其用途
公开(公告)号：US5876524A
公开(公告)日：1999-03-02
申请号：US765590
申请日：1997-04-17
Applicant: Thomas Andersson
Inventor： Thomas Andersson
CPC classification number: G21C3/07 , C22F1/186 , G21Y2002/103 , G21Y2002/206 , G21Y2004/201 , Y02E30/40
Abstract: The present invention relates to a method of manufacturing tubes of zirconium based alloys for usage in nuclear reactors. According to the invention one can achieve good resistance towards general corrosion, improved transversal creep strength and reduced irradiation induced growth by subjecting a .beta.-quenched tube a vacuum anneal in the .alpha.-phase range at a temperature and a time sufficient to obtain an annealing parameter value A in the range 3.4 .times.10.sup.-16 to 3.4 .times.10.sup.-13.
Abstract translation: PCT No.PCT / SE95 / 00749 Sec。 371日期1997年04月17日 102（e）日期1997年4月17日PCT提交1995年6月20日PCT公布。 出版物WO95 / 35395 日期：1995年12月28日本发明涉及一种用于核反应堆的锆基合金管的制造方法。 根据本发明，可以在足以获得退火参数的温度和时间下对β淬灭的管进行α相范围内的真空退火，从而获得对一般腐蚀，改进的横向蠕变强度和减小的辐射诱导生长的良好抵抗力 值A在3.4 x 10-16到3.4 x 10-13之间。
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公开(公告)号：US5802130A
公开(公告)日：1998-09-01
申请号：US880440
申请日：1997-06-27
Applicant: Jean-Paul Mardon , Jean Sevenat , Daniel Charquet
Inventor： Jean-Paul Mardon , Jean Sevenat , Daniel Charquet
CPC classification number: G21C3/07 , G21Y2002/103 , G21Y2004/10 , G21Y2004/201 , Y02E30/40
Abstract: A tube for constituting all or part of a cladding or guide tube for a fuel assembly is made from an alloy containing, by weight, 0.4% to 0.6% of tin, 0.5% to 0.8% of iron, 0.35% to 0.50% of vanadium, and 0.10% to 0.18% of oxygen, 100 ppm to 180 ppm of carbon and 50 ppm to 120 ppm of silicon. The alloy contains nothing else apart from zirconium and unavoidable impurities and it is completely recrystallized.
Abstract translation: 用于构成用于燃料组件的包层或导管的全部或一部分的管由含有重量比为0.4％至0.6％的锡，0.5％至0.8％的铁，0.35％至0.50％的钒的合金制成 ，0.10〜0.18％的氧，100〜180ppm的碳，50〜120ppm的硅。 该合金除了锆和不可避免的杂质外不含其它物质，并且完全重结晶。
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103.发明授权Zirconium-based alloy tube for a nuclear reactor fuel assembly and a process for producing such a tube 失效用于核反应堆燃料组件的锆基合金管和用于生产这种管的方法
公开(公告)号：US5702544A
公开(公告)日：1997-12-30
申请号：US593869
申请日：1996-01-30
Applicant: Jean-Paul Mardon , Jean Sevenat , Daniel Charquet
Inventor： Jean-Paul Mardon , Jean Sevenat , Daniel Charquet
CPC classification number: G21C3/07 , G21Y2002/103 , G21Y2004/10 , G21Y2004/201 , Y02E30/40
Abstract: A tube for constituting all or part of a cladding or guide tube for a fuel assembly is made from an alloy containing, by weight, 1.4% to 0.6% of tin, 0.5% to 0.8% of iron, 0.35% to 0.50% of vanadium, and 0.10% to 0.18% of oxygen, 100 ppm to 180 ppm of carbon and 50 ppm to 120 ppm of silicon. The alloy contains nothing else apart from zirconium and unavoidable impurities and it is completely recrystallized.
Abstract translation: 用于构成用于燃料组件的包层或导管的全部或一部分的管由包含以重量计含有1.4％至0.6％的锡，0.5％至0.8％的铁，0.35％至0.50％的钒的合金制成 ，0.10〜0.18％的氧，100〜180ppm的碳，50〜120ppm的硅。 该合金除了锆和不可避免的杂质外不含其它物质，并且完全重结晶。
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104.发明授权Method of fabricating Zircaloy tubing having high resistance to crack propagation 失效制造具有高抗裂纹扩展能力的Zircaloy管材的方法
公开(公告)号：US5681404A
公开(公告)日：1997-10-28
申请号：US385807
申请日：1995-02-09
Applicant: Ronald Bert Adamson , Gerald Allen Potts
Inventor： Ronald Bert Adamson , Gerald Allen Potts
CPC classification number: G21C3/07 , C22F1/186 , G21Y2002/103 , G21Y2002/104 , G21Y2002/20 , G21Y2002/201 , G21Y2004/20 , G21Y2004/201 , Y02E30/40 , Y10S376/90
Abstract: In a zirconium-alloy fuel element cladding, a method for generating regions of coarse and fine intermetallic precipitates across the cladding wall is provided. The method includes steps of specific heat treatments and anneals that coarsen precipitates in the bulk of the cladding. The method also includes at least one step in which an outer region (exterior) of the cladding is heated to the beta or alpha plus beta phase, while an inner region (interior) is maintained at a temperature at which little or no metallurgical change occurs. This method produces a composite cladding in which the outer region comprises fine precipitates and the inner region comprises coarse precipitates.
Abstract translation: 在锆合金燃料元件包层中，提供了跨越包覆壁产生粗细和金属间析出物的区域的方法。 该方法包括在大部分包层中粗化析出物的特定热处理和退火步骤。 该方法还包括至少一个步骤，其中包层的外部区域（外部）被加热到β或α+β相，而内部区域（内部）保持在很少或不发生冶金变化的温度 。 该方法产生复合包层，其中外部区域包含微细的沉淀物，并且内部区域包括粗大的沉淀物。
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105.发明授权Fuel element for pressurized-water reactor with guide tubes finally heat-treated in two steps 失效用于带有导管的加压水反应器的燃料元件最终在两个步骤中热处理
公开(公告)号：US5677937A
公开(公告)日：1997-10-14
申请号：US762952
申请日：1996-12-10
Applicant: Gunnar Vesterlund , Mats Dahlback
Inventor： Gunnar Vesterlund , Mats Dahlback
CPC classification number: C22F1/186 , G21C21/00 , G21C3/06 , G21Y2002/103 , G21Y2004/201 , Y02E30/40
Abstract: The invention relates to a fuel element for a pressurized-water reactor comprising a number of fuel rods arranged in a square lattice and wherein certain positions in the lattice contain guide tubes for receiving control rods, wherein the fuel element can be used for higher burnup by manufacturing the guide tubes of the element such that their irradiation-induced growth is reduced and their corrosion resistance is increased compared with conventionally manufactured guide tubes. This is achieved by finally heat-treating the guide tubes in two steps, the first step being a beta quenching and the second step a heat treatment in the alpha-phase region.
Abstract translation: 本发明涉及一种用于加压水反应器的燃料元件，其包括以正方形格子布置的多个燃料棒，并且其中格子中的某些位置包含用于接收控制棒的引导管，其中该燃料元件可用于较高的燃耗 制造元件的引导管，使得它们的照射诱导的生长减少，并且与常规制造的导管相比它们的耐腐蚀性增加。 这通过以两个步骤最后热处理导管来实现，第一步是β淬灭，第二步是在α相区域中进行热处理。
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Patent Agency Ranking
公开(公告)号：US5527471A
公开(公告)日：1996-06-18
申请号：US382674
申请日：1995-02-02
Applicant: Glenn T. Hong , Vladimir A. Zilberstein
Inventor： Glenn T. Hong , Vladimir A. Zilberstein
CPC classification number: G21C3/07 , B01J19/02 , B01J3/008 , B01J3/04 , C02F11/08 , C02F11/086 , B01J2219/0236 , G21Y2002/103 , G21Y2004/201 , Y02E30/40
Abstract: A process for hydrothermal oxidation of combustible materials in which, during at least a part of the oxidation, corrosive material is present and makes contact with at least a portion of the apparatus over a contact area on the apparatus. At least a portion of the contact surface area comprises iridium, iridium oxide, an iridium alloy, or a base metal overlaid with an iridium coating. Iridium has been found to be highly resistant to environments encountered in the process of hydrothermal oxidation. Such environments typically contain greater than 50 mole percent water, together with oxygen, carbon dioxide, and a wide range of acids, bases and salts. Pressures are typically about 27.5 to about 1000 bar while temperatures range as high as 800.degree. C.
Abstract translation: 一种用于可燃材料的水热氧化的方法，其中在至少一部分氧化期间存在腐蚀性材料并且在设备的接触区域上与装置的至少一部分接触。 接触表面积的至少一部分包括铱，氧化铱，铱合金或覆盖有铱涂层的贱金属。 铱已被发现对水热氧化过程中遇到的环境具有高度的抗性。 这样的环境通常含有大于50摩尔％的水，以及氧气，二氧化碳和各种酸，碱和盐。 压力通常为约27.5至约1000巴，而温度范围高达800℃。
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公开(公告)号：US5519748A
公开(公告)日：1996-05-21
申请号：US52793
申请日：1993-04-23
Applicant: Ronald B. Adamson , Gerald A. Potts
Inventor： Ronald B. Adamson , Gerald A. Potts
CPC classification number: C22F1/186 , G21C3/07 , G21Y2002/103 , G21Y2002/104 , G21Y2002/20 , G21Y2002/201 , G21Y2004/201 , G21Y2004/30 , G21Y2004/303 , Y02E30/40 , Y10S376/90 , Y10T428/12028
Abstract: A Zircaloy cladding having an outer region comprising fine precipitates and inner region comprising coarse precipitates is provided. The outer region comprises about 10% and the inner region comprises about 90% of the cladding wall thickness. Such Zircaloy tubing is resistant to propagation of cracks and at the same time resistant to corrosion in boiling water reactors (BWR). Resistance to damage caused by the pellet-cladding-interaction can be achieved by standard application of a zirconium or zirconium-alloy liner on the tubing inside surface.
Abstract translation: 提供了具有包含细小析出物的外部区域和包含粗大析出物的内部区域的锆石覆层。 外部区域包括约10％，并且内部区域包括约90％的包层壁厚度。 这种Zircaloy管道对裂缝的传播具有抗性，同时耐沸水反应堆（BWR）中的腐蚀。 通过在管道内表面上标准施用锆或锆合金衬垫可以实现由颗粒包层相互作用引起的损伤的抵抗力。
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108.发明授权Method of fabricating zircalloy tubing having high resistance to crack propagation 失效制造具有高抗裂纹扩展性的锆合金管材的方法
公开(公告)号：US5437747A
公开(公告)日：1995-08-01
申请号：US52791
申请日：1993-04-23
Applicant: Ronald B. Adamson , Gerald A. Potts
Inventor： Ronald B. Adamson , Gerald A. Potts
CPC classification number: G21C3/07 , C22F1/186 , G21Y2002/103 , G21Y2002/104 , G21Y2002/20 , G21Y2002/201 , G21Y2004/20 , G21Y2004/201 , Y02E30/40 , Y10S376/90
Abstract: In a zirconium-alloy fuel element cladding, a method for generating regions of coarse and fine intermetallic precipitates across the cladding wall is provided. The method includes steps of specific heat treatments and anneals that coarsen precipitates in the bulk of the cladding. The method also includes at least one step in which an outer region (exterior) of the cladding is heated to the beta or alpha plus beta phase, while an inner region (interior) is maintained at a temperature at which little or no metallurgical change occurs. This method produces a composite cladding in which the outer region comprises fine precipitates and the inner region comprises coarse precipitates.
Abstract translation: 在锆合金燃料元件包层中，提供了跨越包覆壁产生粗细和金属间析出物的区域的方法。 该方法包括在大部分包层中粗化析出物的特定热处理和退火步骤。 该方法还包括至少一个步骤，其中包层的外部区域（外部）被加热到β或α+β相，而内部区域（内部）保持在很少或不发生冶金变化的温度 。 该方法产生复合包层，其中外部区域包含微细的沉淀物，并且内部区域包括粗大的沉淀物。
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公开(公告)号：US5317608A
公开(公告)日：1994-05-31
申请号：US944672
申请日：1992-09-14
Applicant: English C. Pearcy , Hersh K. Manktala
Inventor： English C. Pearcy , Hersh K. Manktala
CPC classification number: G21F9/32 , G21C19/32 , G21Y2002/60 , G21Y2004/201
Abstract: A method for controlling the release of nuclear fission products (including Mo, Tc, Ru, Rh, and Pd) associated with spent nuclear fuel heats the spent nuclear fuel to a predetermined temperature for a predetermined period of time. The predetermined temperature is sufficiently high to diffuse the nuclear fission products within the spent nuclear fuel and sufficiently low to avoid the release of volatile fission products from within the fuel. The predetermined period of time is sufficiently long to cause an optimal degree of phase redistribution of the nuclear fission products within the spent nuclear fuel. The product of the process is spent nuclear fuel characterized by separation of the nuclear fission products into discrete Mo-Tc-Ru-Rh-Pd phases within the spent nuclear fuel. The Mo-Tc-Ru-Rh-Pd phases make the spent nuclear fuel safer for long-term disposal in geologic repositories.
Abstract translation: 用于控制与乏核燃料相关联的核裂变产物（包括Mo，Tc，Ru，Rh和Pd）的释放的方法将废核燃料加热到预定温度一段预定的时间。 预定温度足够高以使核裂变产物在废核燃料内扩散并且足够低以避免挥发性裂变产物从燃料内释放。 预定的时间长度足以使核裂变产物在废核燃料中的相位重新分配的最佳程度。 该过程的产物是废核燃料，其特征在于将核裂变产物分离成废核燃料中的离散Mo-Tc-Ru-Rh-Pd相。 Mo-Tc-Ru-Rh-Pd相使废核燃料在地质储存库中长期处置更加安全。
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110.发明授权
公开(公告)号：US5304261A
公开(公告)日：1994-04-19
申请号：US913468
申请日：1992-07-15
Applicant: Nobukazu Yamamoto , Kouichi Matsumoto , Junjiro Nakajima , Hideo Maki , Hiromasa Hirakawa , Masahisa Inagaki , Iwao Takase , Nobuhiro Okazaki , Hideaki Ishizaki , Toraki Sakuma
Inventor： Nobukazu Yamamoto , Kouichi Matsumoto , Junjiro Nakajima , Hideo Maki , Hiromasa Hirakawa , Masahisa Inagaki , Iwao Takase , Nobuhiro Okazaki , Hideaki Ishizaki , Toraki Sakuma
CPC classification number: G21C3/324 , C23F1/02 , G21Y2002/103 , G21Y2002/302 , G21Y2004/201 , G21Y2004/40 , Y02E30/40
Abstract: In a method of fabricating a channel box for use in a nuclear reactor, Zr-alloy sheet material is formed into a tubular channel box. The method includes solution heat treatment of the Zr-alloy sheet material including quenching from a temperature at which .beta.-phase is present. After the solution heat treatment, portions of the Zr-alloy sheet are thinned relative to other portions by a non-stressing thinning process, such as chemical etching in a bath. The corrosion resistance imparted by heat treatment is retained, and the heat treatment itself is easily performed on material of uniform thickness.
Abstract translation: 在制造用于核反应堆的通道箱的方法中，将Zr合金板材形成为管状通道箱。 该方法包括：从存在（β）相的温度淬火的Zr合金片材的固溶热处理。 在固溶热处理之后，通过非应力变薄处理，例如在浴中的化学蚀刻，Zr合金板的部分相对于其它部分变薄。 通过热处理赋予的耐腐蚀性得到保持，并且易于对厚度均匀的材料进行热处理。
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