公开(公告)号：USRE43182E1

公开(公告)日：2012-02-14

申请号：US10624757

申请日：1996-07-22

Applicant: Jean-Paul Mardon ,  Jean Senevat ,  Daniel Charquet

Inventor： Jean-Paul Mardon ,  Jean Senevat ,  Daniel Charquet

IPC: G21C3/06

CPC classification number: G21C3/07 ,  G21Y2002/102 ,  G21Y2002/103 ,  G21Y2002/302 ,  G21Y2004/10 ,  G21Y2004/40 ,  Y02E30/40

Abstract: A zirconium alloy tube for forming the whole or the outer portion of a nuclear fuel pencil housing or a nuclear fuel assembly guide tube. The zirconium alloy contains 0.8-1.8 wt. % of niobium, 0.2-0.6 wt. % of tin and 0.02-0.4 wt. % of iron, and has a carbon content of 30-180 ppm, a silicon content of 10-120 ppm and an oxygen content of 600-1800 ppm. The tube may be used when recrystallized or stress relieved.

Abstract translation: 一种用于形成核燃料铅笔盒或核燃料组件引导管的整体或外部的锆合金管。 锆合金含有0.8-1.8wt。 ％的铌，0.2-0.6wt。 锡和0.02-0.4重量％ 的铁，并且具有30-180ppm的碳含量，10-120ppm的硅含量和600-1800ppm的氧含量。 当重结晶或减轻应力时，可以使用该管。

公开(公告)号：US06334963B1

公开(公告)日：2002-01-01

申请号：US09582997

申请日：2000-09-21

Applicant: Xavier Deschanels ,  Philippe Bry ,  Jean-Pierre Koci ,  Bruno Provot

Inventor： Xavier Deschanels ,  Philippe Bry ,  Jean-Pierre Koci ,  Bruno Provot

IPC: G21C724

CPC classification number: G21C7/24 ,  G21Y2002/102 ,  G21Y2002/103 ,  G21Y2002/104 ,  G21Y2004/10 ,  Y02E30/39

Abstract: The invention relates to a neutron absorbent material and a method of manufacturing such a material. The neutron absorbent material of the invention is a material having a high resistance to corrosion and high mechanical strength. This material is based on hafnium diboride and additionally comprises hafnium dioxide. The method of the invention enables one to reduce the sintering temperature of a composite material based on hafnium diboride. It includes a step that consists of mixing hafnium diboride and hafnium dioxide and a step of sintering the mixture obtained.

Abstract translation: 本发明涉及一种中子吸收材料及其制造方法。 本发明的中子吸收材料是具有高抗腐蚀性和高机械强度的材料。 该材料基于二铪二氧化铪，另外还包含二氧化铪。 本发明的方法能够降低基于二硼化铪的复合材料的烧结温度。 它包括由二氯化铪和二氧化铪组成的步骤和烧结混合物的步骤。

公开(公告)号：US5687204A

公开(公告)日：1997-11-11

申请号：US319629

申请日：1994-10-07

Applicant: Katsuyuki Ara ,  Nobuya Nakajima ,  Noriya Ebine

Inventor： Katsuyuki Ara ,  Nobuya Nakajima ,  Noriya Ebine

IPC: G21C13/087 ,  G21C17/003 ,  G21C17/00

CPC classification number: G21C13/087 ,  G21C17/003 ,  G21Y2002/102 ,  G21Y2002/204 ,  Y02E30/40

Abstract: In a method of and an apparatus for checking the degradation of the pressure vessel of a nuclear reactor with the pressure vessel of the nuclear reactor being directly measured in a non-destructive manner, a magnetic yoke having an exciting coil and a magnetic flux measuring coil is closely placed in contact with the inner wall of the pressure vessel of the nuclear reactor. The hysteresis magnetization characteristics of the closed magnetic path formed by the magnetic yoke and the pressure vessel of the nuclear reactor are measured. The coercive forces are obtained by the hysteresis characteristics. The hardness of the material comprising the pressure vessel of the nuclear reactor at the part of the magnetic path formed in the pressure vessel of the nuclear reactor is obtained from the coercive forces and the degradation of the material comprising the pressure vessel is checked from the hardness.

Abstract translation: 在以非破坏性方式直接测量核反应堆的压力容器的核反应堆的压力容器的劣化检测方法和装置中，具有励磁线圈和磁通量测量线圈的磁轭 紧密地与核反应堆的压力容器的内壁接触。 测量由磁轭和核反应堆的压力容器形成的闭合磁路的磁滞特性。 矫顽力通过滞后特性得到。 由核反应堆的压力容器中形成的磁路部分的核反应堆的压力容器的材料的硬度是由矫顽力获得的，并且从包含压力容器的材料的劣化可以从硬度 。

公开(公告)号：US5602888A

公开(公告)日：1997-02-11

申请号：US416656

申请日：1995-04-05

Applicant: Samson Hettiarachchi ,  Thomas P. Diaz ,  Gary P. Wozadlo

Inventor： Samson Hettiarachchi ,  Thomas P. Diaz ,  Gary P. Wozadlo

IPC: G21D1/00 ,  B01J37/03 ,  C23C30/00 ,  C23F11/08 ,  C23F11/18 ,  G01N17/02 ,  G21C3/07 ,  G21C17/02 ,  G21C17/022 ,  G21C19/28 ,  G21C19/30 ,  G21C19/307 ,  G21D3/08 ,  G21C9/00

CPC classification number: G21C17/0225 ,  B01J37/031 ,  C23F11/08 ,  C23F11/18 ,  G01N17/02 ,  G21C17/02 ,  G21C17/022 ,  G21C19/28 ,  G21C19/30 ,  G21C19/307 ,  G21C3/07 ,  G21Y2002/102 ,  G21Y2002/103 ,  G21Y2002/104 ,  G21Y2002/204 ,  G21Y2004/10 ,  G21Y2004/20 ,  G21Y2004/30 ,  G21Y2004/40 ,  Y02E30/40

Abstract: A method for mitigating crack growth on the surface of stainless steel or other alloy components in a water-cooled nuclear reactor wherein a solution or suspension of a compound containing a noble metal is injected into the coolant water while the reactor is not generating nuclear heat, e.g., during shutdown or recirculation pump heatup. During shutdown, the reactor coolant water reaches temperatures as low as 120.degree. F., in contrast to the water temperature of 550.degree. F. during normal operation. During pump heatup, the water temperature reaches 400.degree.-450.degree. F. At these reduced temperatures, the rate of thermal decomposition of the injected noble metal compound is reduced. However, radiation-induced decomposition also occurs inside the reactor. In particular, the noble metal compound can be decomposed by the gamma radiation emanating from the nuclear fuel core of the reactor. The noble metal compound decomposes under reactor thermal and radiation conditions to release ions/atoms of the noble metal which incorporate in or deposit on the oxide film formed on the stainless steel and other alloy components. As a result, the electrochemical potential of the metal surface is maintained at a level below the critical potential in the presence of low levels of hydrogen to protect against intergranular stress corrosion cracking.

Abstract translation: 一种用于减轻水冷核反应堆中不锈钢或其他合金组分表面上的裂纹扩展的方法，其中将含有贵金属的化合物的溶液或悬浮液注入冷却水中，同时反应器不产生核热， 例如在停机或再循环泵加热期间。 在停机期间，反应堆冷却水的温度低至120°F，与正常运行时的550°F水温相反。 在泵加热期间，水温达到400°-450°F。在这些降低的温度下，注入的贵金属化合物的热分解速率降低。 然而，辐射诱导的分解也发生在反应器内部。 特别地，贵金属化合物可以通过从反应器的核燃料芯发出的γ射线分解。 贵金属化合物在反应器热和辐射条件下分解，以释放掺入或沉积在不锈钢和其它合金组分上形成的氧化膜上的贵金属的离子/原子。 因此，在低水平的氢气存在下，金属表面的电化学势能保持在低于临界电位的水平，以防止晶间应力腐蚀开裂。

公开(公告)号：US5247550A

公开(公告)日：1993-09-21

申请号：US858904

申请日：1992-03-27

Applicant: Richard A. Perkins ,  Raymond A. Busch

Inventor： Richard A. Perkins ,  Raymond A. Busch

IPC: G21C3/06 ,  G21C3/07 ,  G21C3/20

CPC classification number: G21C3/07 ,  G21C3/20 ,  G21Y2002/102 ,  G21Y2002/104 ,  G21Y2004/10 ,  G21Y2004/30 ,  Y02E30/40

Abstract: A cladding tube for nuclear fuel having an outer elongated cladding tube and a zirconium liner which lines the outer cladding tube, the inner wall of the liner having an inner diffusion portion of a zirconium based alloy of tin and/or vanadium.

公开(公告)号：US5225154A

公开(公告)日：1993-07-06

申请号：US391316

申请日：1989-08-02

Applicant: Masayoshi Kanno ,  Masahisa Inagaki ,  Iwao Takase ,  Jiro Kuniya ,  Akira Maru ,  Tetsuro Yasuda ,  Hideo Maki

Inventor： Masayoshi Kanno ,  Masahisa Inagaki ,  Iwao Takase ,  Jiro Kuniya ,  Akira Maru ,  Tetsuro Yasuda ,  Hideo Maki

IPC: G21C3/07 ,  G21C3/20 ,  G21C3/30 ,  G21C3/34 ,  G21C3/356

CPC classification number: G21C3/34 ,  G21C3/07 ,  G21C3/20 ,  G21Y2002/102 ,  G21Y2002/103 ,  G21Y2002/104 ,  G21Y2004/10 ,  G21Y2004/201 ,  G21Y2004/202 ,  G21Y2004/30 ,  Y02E30/40

Abstract: A fuel assembly for a nuclear reactor comprising a fuel cladding tube of three-layer structure having an outer surface in contact with reactor water of the nuclear reactor, an inner surface layer in contact with the nuclear fuel, and an intermediate layer interposed between the outer surface layer and the inner surface layer. the outer surface layer is made of a Zr-based alloy containing Nb, Sn and Mo. The inner surface layer is made of pure zirconium. The intermediate layer is made of a high ductility alloy which is higher in ductility than the outer surface layer and is higher in strength than the inner surface layer.

公开(公告)号：US4759896A

公开(公告)日：1988-07-26

申请号：US666697

申请日：1984-10-31

Applicant: William A. Boyd

Inventor： William A. Boyd

IPC: G21C1/08 ,  G21C3/328 ,  G21C5/00 ,  G21C11/00 ,  G21C11/06 ,  G21C7/06

CPC classification number: G21C3/328 ,  G21C11/00 ,  G21C11/06 ,  G21Y2002/102 ,  G21Y2002/201 ,  G21Y2002/501 ,  G21Y2004/30 ,  Y02E30/34 ,  Y02E30/38

Abstract: A method and apparatus is disclosed for reducing the exposure of pressure vessel welds to fast neutron fluxes. Localized peripheral core areas are provided with rod assemblies which may be made up of nuclear absorbing materials, nuclear reflecting materials, or any combination thereof, and of any desired length so as to reduce the exposure of the welds to such fast neutron fluxes. The rod assemblies are precisely tailored consistent with nuclear calculations to provide the desired effect without substantially reducing core ratings or adversely affecting reactor shutdown margins.

Abstract translation: 公开了一种用于减少压力容器焊接对快中子通量的暴露的方法和装置。 本地化的外围芯区域设置有杆组件，其可以由核吸收材料，核反射材料或其任何组合构成，并且具有任何期望的长度，以便减少焊接到这种快中子通量的暴露。 棒组件精确地与核计算一致，以提供期望的效果，而基本上不降低铁芯额定值或不利地影响反应堆关闭余量。

公开(公告)号：US4082609A

公开(公告)日：1978-04-04

申请号：US680924

申请日：1976-04-28

Applicant: Fritz Schweiger

Inventor： Fritz Schweiger

IPC: G21C7/107 ,  G21C7/10

CPC classification number: G21C7/107 ,  G21Y2002/102 ,  G21Y2002/104 ,  G21Y2002/201 ,  G21Y2002/302 ,  G21Y2002/303 ,  G21Y2004/30 ,  G21Y2004/301 ,  Y02E30/33 ,  Y02E30/39

Abstract: In a gas cooled pebble bed reactor the poison part of a control rod which s upper and lower portions and an interior cooling fluid channel is movable into and away from a bed of spherical fuel elements; the improvement includes a control rod security device which facilitates removal of the fractured control rod when the control rod breaks between its end portions. The security device includes an oblong member which is located and extends within the cooling channel and is slack relative to the control rod, a device attached to one end of the oblong member for preventing a fall of the oblong member into the lower portion of the control rod, and a device attached to the other end of the oblong member for preventing portions of the control rod from falling into the bed of fuel elements upon a fracture of the control rod between its end portions. The oblong member is sufficiently strong so as to hold the upper and lower end portions together upon the fracture of the control rod, so that its upper and lower end portions then remain interconnected through the security device.

公开(公告)号：US06919576B2

公开(公告)日：2005-07-19

申请号：US10067708

申请日：2002-02-04

Applicant: Richard N. Wright ,  W. David Swank ,  Ronald E. Mizia

Inventor： Richard N. Wright ,  W. David Swank ,  Ronald E. Mizia

IPC: G21C19/40 ,  G21C11/00

CPC classification number: G21C19/40 ,  G21Y2002/102 ,  G21Y2002/103 ,  G21Y2002/104 ,  G21Y2002/206 ,  G21Y2004/10 ,  G21Y2004/30

Abstract: Thermal neutron absorbing composite coating materials and methods of applying such coating materials to spent nuclear fuel storage systems are provided. A composite neutron absorbing coating applied to a substrate surface includes a neutron absorbing layer overlying at least a portion of the substrate surface, and a corrosion resistant top coat layer overlying at least a portion of the neutron absorbing layer. An optional bond coat layer can be formed on the substrate surface prior to forming the neutron absorbing layer. The neutron absorbing layer can include a neutron absorbing material, such as gadolinium oxide or gadolinium phosphate, dispersed in a metal alloy matrix. The coating layers may be formed by a plasma spray process or a high velocity oxygen fuel process.

Abstract translation: 提供了热中子吸收复合涂层材料以及将这种涂覆材料应用于废核燃料储存系统的方法。 应用于基板表面的复合中子吸收涂层包括覆盖基板表面的至少一部分的中子吸收层和覆盖至少一部分中子吸收层的耐腐蚀顶涂层。 可以在形成中子吸收层之前在衬底表面上形成任选的粘结涂层。 中子吸收层可以包括分散在金属合金基体中的中子吸收材料，例如氧化钆或磷酸钆。 涂层可以通过等离子喷涂法或高速氧燃料法形成。

公开(公告)号：US20030147485A1

公开(公告)日：2003-08-07

申请号：US10067708

申请日：2002-02-04

Applicant: Bechtel BWXT Idaho, LLC

Inventor： Richard N. Wright ,  W. David Swank ,  Ronald E. Mizia

IPC: G21C019/00

CPC classification number: G21C19/40 ,  G21Y2002/102 ,  G21Y2002/103 ,  G21Y2002/104 ,  G21Y2002/206 ,  G21Y2004/10 ,  G21Y2004/30

Abstract: Thermal neutron absorbing composite coating materials and methods of applying such coating materials to spent nuclear fuel storage systems are provided. A composite neutron absorbing coating applied to a substrate surface includes a neutron absorbing layer overlying at least a portion of the substrate surface, and a corrosion resistant top coat layer overlying at least a portion of the neutron absorbing layer. An optional bond coat layer can be formed on the substrate surface prior to forming the neutron absorbing layer. The neutron absorbing layer can include a neutron absorbing material, such as gadolinium oxide or gadolinium phosphate, dispersed in a metal alloy matrix. The coating layers may be formed by a plasma spray process or a high velocity oxygen fuel process.

Abstract translation: 提供了热中子吸收复合涂层材料以及将这种涂覆材料应用于废核燃料储存系统的方法。 应用于基板表面的复合中子吸收涂层包括覆盖基板表面的至少一部分的中子吸收层和覆盖至少一部分中子吸收层的耐腐蚀顶涂层。 可以在形成中子吸收层之前在衬底表面上形成任选的粘结涂层。 中子吸收层可以包括分散在金属合金基体中的中子吸收材料，例如氧化钆或磷酸钆。 涂层可以通过等离子喷涂法或高速氧燃料法形成。