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

IPC: G21C3/326 ,  C22C16/00 ,  C22F1/18 ,  G21C3/06 ,  G21C21/00 ,  G21D1/00

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。

公开(公告)号：US4450016A

公开(公告)日：1984-05-22

申请号：US282061

申请日：1981-07-10

Applicant: Gunnar Vesterlund ,  Erik T. Anderson

Inventor： Gunnar Vesterlund ,  Erik T. Anderson

IPC: C22F1/18 ,  G21C3/07

CPC classification number: G21C3/07 ,  C22F1/186 ,  Y02E30/40 ,  Y10S376/90

Abstract: In the manufacture of cladding tubes of a zirconium-based alloy for fuel rods for nuclear reactors by extrusion of the zirconium-based alloy and cold rollings of the extruded product with annealings, intermediate annealings, between the cold rollings and a .beta.-quenching prior to the last cold rolling, a cladding tube is provided which has at the same time good corrosion properties and mechanical properties by performing the .beta.-quenching prior to a cold rolling, after which an intermediate annealing is performed at a temperature of 500.degree.-610.degree. C.

Abstract translation: 在通过挤出锆基合金制备用于核反应堆的燃料棒的锆基合金的包覆管和通过退火的挤出产品的冷轧，中间退火之间，在冷轧之前和β-淬火之前的β-淬火 最后一次冷轧，提供一种包覆管，同时通过在冷轧之前执行β-淬火同时具有良好的腐蚀性能和机械性能，之后在500〜-660℃的温度下进行中间退火 C。

公开(公告)号：US06512806B2

公开(公告)日：2003-01-28

申请号：US09125411

申请日：1998-11-10

Applicant: Peter Rudling ,  Lars Hallstadius ,  Gunnar Vesterlund

Inventor： Peter Rudling ,  Lars Hallstadius ,  Gunnar Vesterlund

IPC: G21C306

CPC classification number: G21C3/20 ,  G21C3/07 ,  G21Y2002/103 ,  G21Y2002/104 ,  G21Y2002/303 ,  G21Y2004/10 ,  G21Y2004/303 ,  Y02E30/40

Abstract: A component (1) designed for use in a light water reactor and at least partly comprised by a metal and/or a metal alloy presents a coatings (4, 7) at its outer surface (3) and its inner surface(5). The coating (4 and 7 respectively) has as its task to protect the surface (3 and 5 respectively), against oxidation, corrosion, wear and hydration. The coating (4 and 7 respectively) suitably comprises at least one of zirconium dioxide (ZrO2) and zirconium nitride (ZrN).

Abstract translation: 设计用于轻水反应器并且至少部分地由金属和/或金属合金构成的组分（1）在其外表面（3）及其内表面（5）处具有涂层（4,7）。 涂层（分别为4和7）的任务是保护表面（3和5），防止氧化，腐蚀，磨损和水合。 涂层（4和7分别）适当地包括二氧化锆（ZrO 2）和氮化锆（ZrN）中的至少一种。

公开(公告)号：US4364781A

公开(公告)日：1982-12-21

申请号：US235627

申请日：1981-02-18

Applicant: Gunnar Vesterlund

Inventor： Gunnar Vesterlund

IPC: C25D7/04 ,  C23G1/10 ,  C25D5/38 ,  G21C3/20 ,  C23F7/02

CPC classification number: C23G1/106 ,  C25D5/38 ,  G21C3/20 ,  G21Y2002/104 ,  G21Y2004/10 ,  G21Y2004/20 ,  Y02E30/40

Abstract: In the process of applying a layer of copper and a layer of zirconium dioxide to the internal surface of a tube of a zirconium-based alloy, with the layer of zirconium dioxide being located between the copper layer and the internal surface of the tube, the tube surface is first treated with an activating solution in the form of an aqueous solution containing from about 1 to about 3 grams/liter of hydrogen fluoride, from about 2 to about 8 grams/liter of ammonium fluoride and from about 0.1 to about 0.5 gram/liter of sulfuric acid, the amounts of hydrogen fluoride and ammonium fluoride being chosen so that the amount of ammonium fluoride, calculated in moles, exceeds the amount of hydrogen fluoride, calculated in moles, by at least 5 percent.

Abstract translation: 在将铜层和二氧化锆层施加到锆基合金的管的内表面的过程中，二氧化锆层位于铜层和管内表面之间， 管表面首先用含约1至约3克/升氟化氢，约2至约8克/升氟化铵和约0.1至约0.5克的氟化氢水溶液形式的活化溶液处理 /升硫酸，选择氟化氢和氟化铵的量，使得以摩尔计算的氟化铵的量超过以摩尔计算的氟化氢量至少5％。

公开(公告)号：US4233086A

公开(公告)日：1980-11-11

申请号：US964192

申请日：1978-11-28

Applicant: Gunnar Vesterlund

Inventor： Gunnar Vesterlund

IPC: C25D7/04 ,  C23C8/16 ,  C23C26/00 ,  C23C28/00 ,  C25D20060101 ,  G21C3/20 ,  C23F7/02

CPC classification number: G21C3/20 ,  C23C26/00 ,  C23C8/16 ,  Y02E30/40

Abstract: A method for providing a barrier against copper diffusion into a zirconium alloy tube which is lined with copper for the purpose of increasing the resistance of the tube to stress corrosion induced by fission products when the tube is used to fuel a nuclear reactor. The method involves the deposition of a copper lining on the zirconium alloy tube and the subsequent exposure of the lined tube to a substance such as steam, water, nickel oxide or carbon dioxide or another material which has the ability to oxidize the zirconium without oxidizing the copper. Thus, a zirconium oxide layer is developed between the zirconium alloy tube and the copper lining thereon.

Abstract translation: 一种用于提供阻碍铜扩散的阻挡层的方法，该方法是将内衬有铜的锆合金管延伸，以便当管用于燃料核反应堆时，增加管对裂变产物引起的应力腐蚀的阻力。 该方法包括在锆合金管上沉积铜衬里，随后将内衬管暴露于诸如蒸汽，水，氧化镍或二氧化碳的物质或其它具有氧化锆而不氧化的能力的材料 铜。 因此，在锆合金管和其上的铜衬套之间形成氧化锆层。

公开(公告)号：US5654993A

公开(公告)日：1997-08-05

申请号：US564191

申请日：1995-12-18

Applicant: Gunnar Vesterlund ,  Mats Dahlback

Inventor： Gunnar Vesterlund ,  Mats Dahlback

IPC: G21C3/326 ,  C22C16/00 ,  C22F1/18 ,  G21C3/06 ,  G21C21/00 ,  G21D1/00 ,  G21C3/32

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: PCT No.PCT / SE94 / 00644 Sec。 371 1995年12月18日第 102（e）1995年12月18日的PCT PCT 1994年6月29日PCT公布。 公开号WO95 / 01639 日期1995年1月12日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，其中该燃料元件可以 用于通过制造元件的引导管以使其照射诱导的生长减少并且与常规制造的引导管相比它们的耐腐蚀性增加而用于更高的燃耗。 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。

公开(公告)号：US5242622A

公开(公告)日：1993-09-07

申请号：US655994

申请日：1991-02-15

Applicant: Jean Boutin ,  Airy-Pierre Lamaze ,  Gunnar Vesterlund

Inventor： Jean Boutin ,  Airy-Pierre Lamaze ,  Gunnar Vesterlund

IPC: G21C7/24 ,  G21C21/18

CPC classification number: G21C7/24 ,  G21C21/18 ,  Y02E30/39

Abstract: The invention relates to a process for the production of a neutron absorbing pellet for use in a nuclear reactor control device, comprising the following stages:a) compactable products are prepared incorporating as % by weight electrolytic crystals or chips of Hf and optionally boron carbide powder with a total weight (HF+B.sub.4 C) of 40 to 100%, the Hf:(Hf+B.sub.4 C) ratio being 0.20 to 1 and optionally other metallic elements melting at above 400.degree. C.;b) these products are mixed and compressed in a mould in one or more filling and compression operations until a pellet is obtained with an apparent density higher than 80% of its average density in the solid state;c) a sintering treatment is optionally carried out on said pellet;d) the pellet is or has been extracted from the mould;e) the pellet is optionally ground.

Abstract translation: 本发明涉及一种用于生产用于核反应堆控制装置的中子吸收颗粒的方法，包括以下阶段：a）制备可压实的产品，其以重量％的电解晶体或Hf的芯片和任选的碳化硼粉末 总重量（HF + B4C）为40〜100％，Hf：（Hf + B4C）比为0.20〜1，任意其它熔点高于400℃的金属元素。 b）将这些产品在一个或多个填充和压缩操作中在模具中混合和压缩，直到获得具有高于固态平均密度的80％的表观密度的颗粒; c）任选地在所述颗粒上进行烧结处理; d）颗粒已经或已经从模具中提取出来; e）任选研磨颗粒。

公开(公告)号：US4888150A

公开(公告)日：1989-12-19

申请号：US291254

申请日：1988-12-28

Applicant: Gunnar Vesterlund

Inventor： Gunnar Vesterlund

IPC: G21C7/10 ,  G21C7/113

CPC classification number: G21C7/113 ,  G21Y2002/201 ,  G21Y2002/206 ,  G21Y2004/30 ,  Y02E30/39

Abstract: A control rod for a nuclear reactor comprising a number of absorber plates (13-16) which are connected to each other along a center line on the control rod and which are each provided with a plurality of bored channels (18b), which extend at least substantially perpendicularly to the center line of the rod, contain boron carbide or other absorber material which swells upon irradiation and are sealed off from communication with the surroundings of the control rod. Within at least one region of an absorber plate, each channel is arranged at a smaller distance to an adjacent channel than to the surface of the absorber plate. Preferably, each channel within the stated region of the absorber plate is arranged at a smaller distance to the adjacent channel on one of its sides than to the adjacent channel on its other side.

Abstract translation: 一种用于核反应堆的控制棒，包括多个吸收板（13-16），它们沿着控制棒上的中心线相互连接并且分别设置有多个钻孔通道（18b） 至少基本上垂直于杆的中心线，包含碳化硼或其他吸收材料，其在照射时溶胀并且与控制棒的周围环境密封。 在吸收板的至少一个区域内，每个通道相对于吸收板的表面以比相邻通道更小的距离布置。 优选地，吸收器板的规定区域内的每个通道布置在与其一侧上的相邻通道更小的距离处，而不是在另一侧上的相邻通道。

公开(公告)号：US4450020A

公开(公告)日：1984-05-22

申请号：US432687

申请日：1982-10-04

Applicant: Gunnar Vesterlund

Inventor： Gunnar Vesterlund

IPC: C22F1/18 ,  G01L1/26

CPC classification number: C22F1/186 ,  G01L1/26 ,  Y10S376/90

Abstract: In the manufacture of cladding tubes of a zirconium-based alloy for fuel rods for nuclear reactors by extrusion of the zirconium-based alloy and cold rollings of the extruded product with annealings, intermediate annealings, between the cold rollings and a .beta.-quenching of the extruded product prior to the last cold rolling, a cladding tube is provided which has at the same time good corrosion properties and mechanical properties by performing the .beta.-quenching prior to a cold rolling, after which an intermediate annealing is performed at a temperature of 500.degree.-675.degree. C., and preferably at a temperature of 500.degree.-610.degree. C. The zirconium-based alloy is a zirconium-tin alloy comprising 1.2-1.7% tin, 0.07-0.24% iron, 0.05-0.15% chromium and 0-0.08% nickel.

Abstract translation: 在通过挤出锆基合金的用于核反应堆的燃料棒的锆基合金的包覆管的制造和具有退火的挤出产品的冷轧，中间退火之间，冷轧之间的β淬火 在最后一次冷轧之前的挤出产品，提供了一种包覆管，同时通过在冷轧之前进行β-淬火同时具有良好的腐蚀性能和机械性能，之后在500℃的温度下进行中间退火 DEG -75℃，优选在500℃-610℃的温度下进行。锆基合金是一种锆锡合金，其包含1.2-1.7％的锡，0.07-0.24％的铁，0.05-0.15％的铬和 0-0.08％镍。