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

IPC: G21C19/32 ,  G21F9/32 ,  G21F9/30

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。

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

IPC: C22F1/00 ,  C22F1/18 ,  C23F1/02 ,  G21C3/324 ,  G21C21/00

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。

公开(公告)号：US4990305A

公开(公告)日：1991-02-05

申请号：US372483

申请日：1989-06-28

Applicant: John P. Foster ,  Charles S. Cook ,  George P. Sabol

Inventor： John P. Foster ,  Charles S. Cook ,  George P. Sabol

IPC: G21C3/06 ,  B21B21/00 ,  B21D39/08 ,  C22C16/00 ,  C22F1/00 ,  C22F1/18 ,  G21C3/07

CPC classification number: G21C3/07 ,  C22F1/186 ,  B21B21/00 ,  G21Y2002/104 ,  G21Y2004/20 ,  G21Y2004/201 ,  Y02E30/40 ,  Y10S72/70

Abstract: A method of producing enhanced radial texture in zirconium alloy tubing suitable for use in forming cladding for nuclear fuel rods is provided. The tubing production method described herein employs a combination of mechanical expansion and heat treatment steps in the final stage of tubing formation to produce a single peak radial texture in the tubing, thereby imparting enhanced resistance to pellet-cladding-interaction to the finished tubing. The tubing is preferably processed to a diameter within less than about 10 to 20% of the desired final diameter, annealed, and expanded less than about 10 to 20% to the desired final diameter, thereby producing a unique radial texture in the finished tubing. In an alternative method, the finally expanded tubing is subjected to a final recrystallization anneal to produce a significantly enhanced split radial texture.

公开(公告)号：US4849082A

公开(公告)日：1989-07-18

申请号：US825407

申请日：1986-02-03

Applicant: David L. Baty ,  William C. Young ,  David E. Lewis

Inventor： David L. Baty ,  William C. Young ,  David E. Lewis

IPC: C23C14/16 ,  C23C14/14 ,  C23C14/34 ,  C23C14/48 ,  C23C14/58 ,  G21C3/07 ,  G21C3/30

CPC classification number: C23C14/16 ,  C23C14/48 ,  C23C14/58 ,  C23C14/5806 ,  C23C14/5833 ,  C23C14/5893 ,  G21C3/07 ,  G21Y2002/103 ,  G21Y2004/10 ,  G21Y2004/201 ,  G21Y2004/40 ,  Y02E30/40

Abstract: An implantation method for the improvement of the corrosion resistance and hydrogen absorption resistance of zirconium alloys in a light water nuclear reactor environment includes the steps of sputtering a layer of hafnium ions onto a zirconium alloy and the implanting the hafnium ions with xenon doses of 3.times.10.sup.16 ions/cm.sup.2.

Abstract translation: 一种用于提高锆合金在轻水核反应堆环境中的耐腐蚀性和耐氢吸收性的植入方法包括以下步骤：将铪离子层溅射到锆合金上，并用氙剂量的3×1016离子注入铪离子 / cm2。

公开(公告)号：US4717427A

公开(公告)日：1988-01-05

申请号：US817187

申请日：1986-01-08

Applicant: Michel Morel ,  Jean-Paul Mardon

Inventor： Michel Morel ,  Jean-Paul Mardon

IPC: C22F1/00 ,  C22F1/18 ,  G21C3/34

CPC classification number: C22F1/186 ,  G21C3/3424 ,  G21Y2002/104 ,  G21Y2002/302 ,  G21Y2004/20 ,  G21Y2004/201 ,  G21Y2004/202 ,  Y02E30/40

Abstract: For manufacturing zirconium alloy plates, more particularly for forming grids for holding nuclear fuel elements, a strip is obtained by hot rolling, then cold rolling, with a high cold hammering rate, then the strip is subjected to reheating for removing the tension at a temperature lower than the recrystallization temperature. Plates are cut out in the transverse direction of the strip.

Abstract translation: 为了制造锆合金板，更特别地，用于形成用于保持核燃料元件的格栅，通过热轧，然后冷轧，以高的冷锤击速率获得条带，然后将带材进行再加热以在温度下去除张力 低于再结晶温度。 在条带的横向上切割板。

公开(公告)号：US4606109A

公开(公告)日：1986-08-19

申请号：US570487

申请日：1984-01-13

Applicant: Albert Weiss

Inventor： Albert Weiss

IPC: G21C3/06 ,  G21C7/10 ,  B23P17/00

CPC classification number: G21C7/10 ,  G21C3/06 ,  G21Y2002/104 ,  G21Y2004/201 ,  G21Y2004/40 ,  Y02E30/39 ,  Y10T29/49805 ,  Y10T29/49929

Abstract: The zirconium cladding of a coolant-displacement rod of a nuclear reactor is precollapsed in the zirconium oxide stack of pellets which supports the cladding. Current is conducted through the cladding in an atmosphere at reduced pressure containing residual oxygen, to heat the cladding to a temperature at which its yield strength is reduced. Then, while the rod remains at this temperature, it is subjected to isostatic pressure which collapses the cladding uniformly. The formation, by reason of exposure to neutron flux, of a long unsupported gap in the cladding which might be collapsed under the pressure of the coolant is precluded. In addition, the rod retains its symmetry. The outer surface of the cladding is oxidized, facilitating the movement of the rod into its thimbles of the core and improving the resistances of the cladding to reaction with the coolant.

公开(公告)号：US4226647A

公开(公告)日：1980-10-07

申请号：US914829

申请日：1978-06-12

Applicant: Erland M. Schulson ,  Donald J. Cameron

Inventor： Erland M. Schulson ,  Donald J. Cameron

IPC: C22C16/00 ,  C22F1/18 ,  G21C1/20 ,  G21C3/06 ,  G21C3/07 ,  G21C13/08 ,  C21D1/02

CPC classification number: G21C3/07 ,  C22C16/00 ,  C22F1/186 ,  G21C1/20 ,  G21C3/06 ,  G21Y2002/103 ,  G21Y2002/104 ,  G21Y2004/101 ,  G21Y2004/201 ,  Y02E30/40

Abstract: High tensile strength, creep and corrosion resistant zirconium alloys containing 7.0-10.0 wt % aluminum, 0-3 wt % in total of one or more elements selected from the group consisting of magnesium, tin, chromium, iron, carbon, silicon, yttrium, niobium, molybdenum and beryllium, the balance zirconium and incidental impurities, are produced by annealing cast alloys at a temperature below about 992.degree. C. for a period of time sufficient to produce alloys having a substantially continuous matrix of the ordered intermetallic compound Zr.sub.3 Al. The alloys may initially be hot worked at temperatures about 1000.degree. C., while in the .beta.Zr-Zr.sub.2 Al two phase region, prior to annealing. Preferred alloys contain 7.5-9.5 wt % aluminum, the balance zirconium and incidental impurities.

Abstract translation: 含有7.0-10.0重量％铝的高抗拉强度，蠕变和耐腐蚀的锆合金，0-3重量％的总计选自镁，锡，铬，铁，碳，硅，钇， 铌，钼和铍，余量为锆和附带杂质，通过在低于约992℃的温度下退火铸造合金制造足够长的时间，足以产生具有基本连续的有序金属间化合物Zr 3 Al基体的合金。 该合金最初可以在退火前在约1000℃的温度下热处理，而在βZr-Zr2Al两相区域。 优选的合金含有7.5-9.5重量％的铝，余量为锆和附带的杂质。

公开(公告)号：US4094706A

公开(公告)日：1978-06-13

申请号：US711744

申请日：1976-08-04

Applicant: Erland Maxwell Schulson ,  Donald James Cameron

Inventor： Erland Maxwell Schulson ,  Donald James Cameron

IPC: C22C16/00 ,  G21C1/20 ,  G21C3/06 ,  G21C3/07 ,  C21D1/02

CPC classification number: G21C3/07 ,  C22C16/00 ,  G21C1/20 ,  G21C3/06 ,  G21Y2002/103 ,  G21Y2002/104 ,  G21Y2004/101 ,  G21Y2004/201 ,  Y02E30/40 ,  Y10S376/90

Abstract: High tensile strength, creep and corrosion resistant zirconium alloys containing 7.0-10.0 wt% aluminum, 0-3 wt% in total of one or more elements selected from the group consisting of magnesium, tin, chromium, iron, carbon, silicon, yttrium, niobium, molybdenum and beryllium, the balance zirconium and incidental impurities, are produced by annealing cast alloys at a temperature below about 992.degree. C for a period of time sufficient to produce alloys having a substantially continuous matrix of the ordered intermetallic compound Zr.sub.3 Al. The alloys may initially be hot worked at temperatures above about 1000.degree. C, while in the .beta.Zr-Zr.sub.2 Al two phase region, prior to annealing. Preferred alloys contain 7.5-9.5% aluminum, the balance zirconium and incidental impurities.

Abstract translation: 含有7.0-10.0重量％铝的高抗拉强度，蠕变和耐腐蚀的锆合金，0-3重量％的总计选自镁，锡，铬，铁，碳，硅，钇， 铌，钼和铍，余量为锆和杂质，是通过在低于约992℃的温度下退火铸造合金一段足以产生具有基本上连续的有序金属间化合物Zr 3 Al基体的合金的时间产生的。 该合金最初可以在高于约1000℃的温度下热处理，而在βZr-Zr2Al两相区域中，退火之前。 优选的合金含有7.5-9.5％的铝，余量为锆和附带的杂质。

公开(公告)号：US1644370A

公开(公告)日：1927-10-04

申请号：US73596224

申请日：1924-09-04

Applicant: ALOIS GASCHLER

Inventor： ALOIS GASCHLER

IPC: G21G1/04

CPC classification number: G21G1/04 ,  G21Y2004/201