公开(公告)号：US5377246A

公开(公告)日：1994-12-27

申请号：US967642

申请日：1992-10-28

Applicant: Ira N. Taylor, Jr. ,  Donald C. Wadekamper

Inventor： Ira N. Taylor, Jr. ,  Donald C. Wadekamper

IPC: G21C3/07 ,  G21C3/18 ,  G21C3/20 ,  G21C3/28 ,  G21C3/00

CPC classification number: G21C3/18 ,  Y02E30/40

Abstract: A barrier tube of non-circular cross section is arranged in the space between the stainless steel cladding and metal fuel slugs of a liquid metal reactor. The non-circular shape of this barrier design promotes improved thermal bonding in both the cladding/barrier and barrier/fuel interface regions. The non-circular barrier results in three areas with liquid metal thermal bond gaps having an angle which approaches that for a metal fuel pin without a barrier. Thus, the degree of circumferential unbonding will be less than that which results in localized fuel melting during radiation.

Abstract translation: 在液态金属反应器的不锈钢包层和金属燃料块之间的空间中布置有非圆形横截面的阻挡管。 该阻挡设计的非圆形形状促进了包层/屏障和阻挡/燃料界面区域中的改善的热粘合。 非圆形障碍导致三个区域，其中液态金属热粘合间隙的角度接近金属燃料销而没有屏障的角度。 因此，周向未结合的程度将小于在辐射期间局部燃料熔化的程度。

公开(公告)号：US5274686A

公开(公告)日：1993-12-28

申请号：US951395

申请日：1992-09-25

Applicant: William J. Bryan

Inventor： William J. Bryan

IPC: G21C3/07 ,  G21C3/00

CPC classification number: G21C3/07 ,  G21Y2002/101 ,  G21Y2004/20 ,  G21Y2004/40 ,  Y02E30/40

Abstract: A method for enhancing the wear and corrosion resistance of a tubular nuclear fuel assembly component (40), comprising the step of coating the component with a corrosion and wear resistant material by an anodic arc plasma deposition process (70). The coating is preferably a nitride reactively formed during the plasma deposition process. The component is preferably a nuclear fuel rod cladding tube and the coating material is one of ZrN or TiN.

Abstract translation: 一种用于提高管状核燃料组件部件（40）的耐磨损和耐腐蚀性的方法，包括通过阳极电弧等离子体沉积工艺（70）用耐腐蚀和耐磨材料涂覆部件的步骤。 涂层优选是在等离子体沉积工艺期间反应形成的氮化物。 该组件优选为核燃料棒包覆管，涂层材料为ZrN或TiN之一。

公开(公告)号：US5194101A

公开(公告)日：1993-03-16

申请号：US494638

申请日：1990-03-16

Applicant: Samuel A. Worcester ,  James P. Dougherty ,  John P. Foster

Inventor： Samuel A. Worcester ,  James P. Dougherty ,  John P. Foster

IPC: C22F1/00 ,  C22F1/18 ,  G21C3/07

CPC classification number: C22F1/186

Abstract: This is an improved method of fabricating Zircaloy-4 strip. The method is of the type wherein Zircaloy-4 material is vacuum melted, forged, hot reduced, beta-annealed, quenched, hot rolled, subjected to a post-hot-roll anneal and then reduced by at least two cold rolling steps, including a final cold rolling to final size, with intermediate annealing between the cold rolling steps and with a final anneal after the last cold rolling step. The improvement comprises: (a) utilizing a maximum processing temperature of 620.degree. C. between the quenching and the final cold rolling to final size; (b) utilizing a maximum intermediate annealing temperature of 520.degree. C.; and (c) utilizing hot rolling, post-hot-roll annealing, intermediate annealing and final annealing time-temperature combinations to give an A parameter of between 4.times.10.sup.-19 and 7.times.10.sup.-18 hour, where segment parameters are calculated for the hot rolling step and each annealing step, the segment parameters are calculated by taking the time, in hours, for which that step is performed, to the (-40,000/T) power, in which T is the temperature, in degrees K, at which the step is performed, and where the A parameter is the sum of the segment parameters. Preferably, the hot rolling and the post-hot-roll anneal are at 560.degree.-620.degree. C. and are for 1.5-3 hours and the intermediate annealing is at 400.degree.-520.degree. C. and is for 1.5-15 hours and the final anneal after the last cold rolling step is at 560.degree.-710.degree. C. for 1-5 hours, and the beta-anneal is at 1015.degree.-1130.degree. C. for 2-30 minutes.

公开(公告)号：US5116569A

公开(公告)日：1992-05-26

申请号：US563697

申请日：1990-08-07

Applicant: Shigeki Kasahara ,  Kiyotomo Nakata ,  Jiro Kuniya ,  Shigeo Hattori

Inventor： Shigeki Kasahara ,  Kiyotomo Nakata ,  Jiro Kuniya ,  Shigeo Hattori

IPC: G21C3/07 ,  C22C38/00 ,  C22C38/40 ,  C22C38/58 ,  G21B1/11 ,  G21B1/17 ,  G21C3/30 ,  G21C7/12 ,  G21C13/08

CPC classification number: C22C38/58 ,  Y10S376/90

Abstract: An austenitic steel excellent in resistance to neutron irradiation embrittlement which contains, by weight, not more than 0.03% carbon, not more than 1% silicon, 5 to 25% manganese, 15 to 26% chromium, and 10 to 20% nickel, the ratio of atomic volume of chromium to the average atomic volume of matrix of the steel being from 0.900 to 1.030. It is possible to add to the austenitic steel, besides the above-mentioned alloying elements, at least one element selected from the group consisting of niobium, titanium, zirconium, tantalum and vanadium which are effective in corrosion resistance and irradiation embrittlement under neutron irradiation in total amounts of not more than 1.0%. At least one of components composing the inside of a nuclear reactor or nuclear fusion reactor is made of the austenitic steel.

公开(公告)号：US5112573A

公开(公告)日：1992-05-12

申请号：US399662

申请日：1989-08-28

Applicant: John P. Foster ,  Robert J. Comstock ,  Samuel A. Worcester ,  George P. Sabol

Inventor： John P. Foster ,  Robert J. Comstock ,  Samuel A. Worcester ,  George P. Sabol

IPC: C22C16/00 ,  C22F1/00 ,  C22F1/18 ,  G21C3/07

CPC classification number: G21C3/07 ,  C22C16/00 ,  C22F1/186 ,  G21Y2002/103 ,  G21Y2004/10 ,  G21Y2004/20 ,  Y02E30/40

Abstract: This is an alloy comprising, by weight percent, 0.5-2.0 niobium, 0.7-1.5 tin, 0.07-0.14 iron, and 0.03-0.14 of at least one of nickel and chromium, and at least 0.12 total of iron, nickel and chromium, and up to 220 ppm C, and the balance essentially zirconium. Preferably, the alloy contains 0.03-0.08 chromium, and 0.03-0.08 nickel. The alloy is also preferably subjected intermediate recrystallization anneals at a temperature of about 1200.degree.-1300.degree. F., and to a beta quench two steps prior to final size.

公开(公告)号：US5080861A

公开(公告)日：1992-01-14

申请号：US543020

申请日：1990-07-25

Applicant: Anand M. Garde

Inventor： Anand M. Garde

IPC: C22C16/00 ,  G21C3/07

CPC classification number: C22C16/00 ,  G21C3/07 ,  G21Y2002/103 ,  G21Y2004/10 ,  Y02E30/40

Abstract: An improved corrosion resistant ductile modified zirconium alloy for extended burnups in water-moderated nuclear reactor core structural components, fuel cladding and analogous corrosive environment uses is provided. It comprises:measurable amounts of niobium in a range up to 0.6 percent by weight, measurable amounts on antimony in a range up to 0.2 percent by weight, measurable amounts of tellurium in a range up to 0.2 percent by weight, tin in the range 0.5 to 1.0 percent by weight, iron in the range 0.18 to 0.24 percent by weight, chromium in the range 0.07 to 0.13 percent by weight, oxygen in the range of from 900 to 2,000 ppm, nickel in an amount less than 70 ppm, carbon in an amount less than 200 ppm and the balance zirconium and minor amounts of impurities.The alloy structure is substantially alpha phase with some precipitated second phase particles which are preferably within the size range of 1200 to 1800 angstroms. Bismuth may be substituted for part of either or both of the elements antimony or tellurium in a range up to 0.2 percent by weight of bismuth.

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：US4986957A

公开(公告)日：1991-01-22

申请号：US356474

申请日：1989-05-25

Applicant: Dale F. Taylor

Inventor： Dale F. Taylor

IPC: C22C16/00 ,  G21C3/07

CPC classification number: C22C16/00 ,  G21C3/07 ,  G21Y2002/103 ,  G21Y2004/10 ,  G21Y2004/20 ,  Y02E30/40

Abstract: Zirconium-based corrosion resistant alloys for use primarily as a cladding material for fuel rods in a boiling water nuclear reactor consist essentially of by weight percent about 0.5 to 2.0 percent thin, about 0.24 to 0.40 percent of a solute composed of copper, nickel and iron, wherein the copper is at least 0.05 percent, and the balance zirconium. Nuclear fuel elements for use in the core of a nuclear reactor have improved corrosion resistant cladding made from these zirconium alloys or composite claddings have a surface layer of the corrosion resistant zirconium alloys metallurgically bonded to the outside surface of a Zircaloy alloy tube. The claddings may contain an inner barrier layer of moderate purity zirconium metallurigcally bonded on the inside surface of the cladding to procide protection from fission products and gaseous impurities generated by the enclosed nuclear fuel.

公开(公告)号：US4938920A

公开(公告)日：1990-07-03

申请号：US216829

申请日：1988-07-08

Applicant: Friedrich Garzarolli ,  Erhard Ortlieb ,  Eckard Steinberg ,  Hans Weidinger

Inventor： Friedrich Garzarolli ,  Erhard Ortlieb ,  Eckard Steinberg ,  Hans Weidinger

IPC: C22C16/00 ,  G21C3/07

CPC classification number: C22C16/00 ,  G21C3/07 ,  Y02E30/40 ,  Y10S376/90

Abstract: A nuclear reactor fuel assembly includes a fuel rod containing nuclear fuel in a cladding tube formed of an iron-containing zirconium alloy. A fuel assembly skeleton to which the fuel rod is attached has a structural part formed of the iron-containing zirconium alloy. The iron-containing zirconium alloy has an oxygen content of from 0.1 to 0.16% by weight and contains alloy components of from 0 to 1% by weight of niobium, 0 to 0.8% by weight of tin, at least two metals from the group consisting of iron, chromium and vanadium having from 0.2 to 0.8% by weight of iron, 0 to 0.4% by weight of chromium and 0 to 0.3% by weight of vanadium, a total percent by weight of iron, chromium and vanadium of from 0.25 to 1% by weight, and a total percent by weight for niobium and tin in the range from 0 to 1% by weight.

Abstract translation: 核反应堆燃料组件包括在含铁锆合金形成的包层管中含有核燃料的燃料棒。 安装燃料棒的燃料组件骨架具有由含铁锆合金形成的结构部分。 含铁锆合金的氧含量为0.1〜0.16重量％，含有0〜1重量％的铌，0〜0.8重量％的锡的合金成分，至少2种以上的金属 的铁，铬和钒，其具有0.2至0.8重量％的铁，0至0.4重量％的铬和0至0.3重量％的钒，铁，铬和钒的总重量百分比为0.25至 1重量％，铌和锡的总重量百分比在0至1重量％的范围内。

公开(公告)号：US4873117A

公开(公告)日：1989-10-10

申请号：US97984

申请日：1987-09-18

Applicant: Dominique Hertz ,  Jean-Michel Couturier

Inventor： Dominique Hertz ,  Jean-Michel Couturier

IPC: C23C8/38 ,  G21C3/07

CPC classification number: C23C8/38 ,  G21C3/07 ,  Y02E30/40 ,  Y10S376/90

Abstract: A sheath for a nuclear reactor control rod consists of chromium nickel stainless steel. It is protected against friction wear by nitridation over a depth of from 15 to 50 .mu.m obtained by an electric discharge in a nitrogen containing atmosphere.

Abstract translation: 用于核反应堆控制棒的护套由铬镍不锈钢组成。 通过在含氮气氛中的放电获得的深度为15至50μm的氮气保护免受摩擦磨损。