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Matches 101 - 150 out of 1,334

Document Document Title
WO/2001/068246A1
An inexpensive, highly catalytic material preferably formed by a leaching process. The catalyst comprises a finely divided metal particulate and a support. The active material may be a nickel and/or nickel alloy particulate having a part...  
WO/2001/068557A1
The invention concerns a method for assembling at least two parts made of materials based on silicon carbide by non-reactive refractory brazing, which consists in contacting said parts with a non-reactive brazing composition and heating ...  
WO/2001/061062A1
A corrosion resistant zirconium based alloy for use in nuclear fuel cladding is made of a low tin content zirconium alloy consisting essentially of: by weight percent, 0.60-2.0 Nb; when Sn is 0.25, then Fe is 0.50; when Sn is 0.40, then ...  
WO/2001/038592A1
The invention concerns an alloy containing at least 95 wt. % of zirconium and between 0.01 and 0.1 wt. % of sulphur and optionally at least one of the elements from the group consisting of: tin, iron, chromium, hafnium, niobium, nickel, ...  
WO/2001/024193A1
The invention concerns a zirconium alloy, containing, besides unavoidable impurities, 0.02 to 1 % iron, 0.8 to 2.3 % niobium, less than 2000 ppm of tin, less than 2000 ppm of oxygen, less than 100 ppm of carbon, from 5 to 35 ppm of sulph...  
WO/2001/024194A1
The invention concerns a zirconium alloy for nuclear reactor components, containing, besides the unavoidable impurities, 0.02 to 1 % iron, 0.8 to 2.3 % niobium, less than 2000 ppm of tin, less than 2000 ppm of oxygen, less than 100 ppm o...  
WO2000065117A8
The present invention relates to a zirconium-based alloy that comprises the following elements: from 0.5 to 3.0 wt % of niobium; from 0.5 to 2.0 wt % of tin; from 0.3 to 1.0 wt % of iron; from 0.002 to 0.2 wt % of chromium; from 0.003 to...  
WO/2001/009402A1
A zirconium alloy for nuclear fuel assemblies which contains iron, chromium, tin, and niobium. The alloy further contains oxygen purposely incorporated. The proportions of these elements are effective in improving both strength and corro...  
WO2000068469A3
A composite metal object comprises ductile crystalline metal particles in an amorphous metal matrix. An alloy is heated above its liquidus temperature. Upon cooling from the high temperature melt, the alloy chemically partitions, forming...  
WO/2000/068448A1
The present invention is a medical implant or device (2) fabricated, in any manner, from a niobium (Nb) - titanium(Ti) - zirconium(Zr) - Molybednum(Mo) alloy (NbTiZrMo alloy). The implant or device has components at least partially fabri...  
WO/2000/068469A2
A composite metal object comprises ductile crystalline metal particles in an amorphous metal matrix. An alloy is heated above its liquidus temperature. Upon cooling from the high temperature melt, the alloy chemically partitions, forming...  
WO/2000/065116A1
The present invention relates to a zirconium-based alloy which is intended for elements used in nuclear reactor cores and comprises the following elements: from 0.5 to 3.0 wt % of niobium; from 0.005 to 0.5 wt % of iron; from 0.03 to 0.2...  
WO/2000/065117A1
The present invention relates to a zirconium-based alloy that comprises the following elements: from 0.5 to 3.0 wt % of niobium; from 0.5 to 2.0 wt % of tin; from 0.3 to 1.0 wt % of iron; from 0.002 to 0.2 wt % of chromium; from 0.003 to...  
WO/2000/061828A1
A modified Ti-V-Zr-Ni-Mn-Cr electrochemical hydrogen storage alloy which has at least one of the following characteristics: 1) an increased charge/discharge rate capability over that the base Ti-V-Zr-Ni-Mn-Cr electrochemical hydrogen sto...  
WO/2000/048199A1
The invention concerns a method for making flat thin elements which consists in: producing a zirconium alloy blank also containing, besides the inevitable impurities, 0.8 to 1.3 % of niobium, 1100 to 1800 ppm of oxygen, and 10 to 35 ppm ...  
WO/2000/046414A1
The invention concerns a zirconium and niobium alloy comprising erbium as burnable neutron poison. The invention also concerns a method for preparing and transforming said alloy and a component containing said alloy. Said alloy is partic...  
WO/2000/036170A1
A zirconium-based alloy, suitable for use in a corrosive environment, where it is subjected to increased radiation and comprises 0.5-1.6 percentage by weight Nb and 0.3-0.6 percentage by weight Fe. The alloy is characterised in that it c...  
WO/2000/036175A1
An amorphous zirconium alloy with excellent corrosion resistance which has a composition represented by the formula Zr¿1-a-b-c?A¿a?[(Fe, Co, Ni)Cu]¿b?Nb¿c?, the formula Zr¿1-a-b-c?A¿a?[(Fe, Co, Ni)Cu]¿b?Ta¿c?, or the formula Zr¿...  
WO/2000/029633A1
A method for producing a component intended to be subjected to an increased radiation in a corrosive environment, wherein the component includes an alloy which at a first, high temperature has a BCC-structure and which at a second, lower...  
WO/2000/026425A1
An amorphous zirconium alloy which has a composition represented by the formula Zr-Al¿a?-Ni¿b?-Cu¿c?-M¿d? (wherein M is at least one element selected from the group consisting of Ti, Nb, and Pd; a, b, c, and d respectively are number...  
WO/1999/066088A1
A zirconium based alloy for use in nuclear fuel components for light-water reactors, the alloy containing, apart from zirconium and normal contents of impurities in zirconium of reactor quality, the alloy elements Sn, Fe, Cr, and Ni, the...  
WO/1999/050854A1
The invention concerns a method for making tubes designed for a nuclear fuel pencil case or guide tube which consists in forming a bar in a zirconium based alloy containing equally 0.3 to 0.25 wt. % of the total iron, of chromium or vana...  
WO/1998/040311A1
A method is provided for cracking ammonia to produce hydrogen. The method includes the steps of passing ammonia over an ammonia-cracking catalyst which is an alloy including (1) alloys having general formula Zr�1-x?Ti�x?M�1?M�2?,...  
WO/1998/032896A1
The invention relates to an anti-corrosion coating for magnesium materials, consisting of an alloy containing (A) a base material of at least one of the following metals: aluminium, titanium, magnesium or zirconium and (B) at least one a...  
WO/1998/010427A1
The invention concerns guide tubes (6) for zirconium alloy control elements (zircaloy-2 and zircaloy-4) in pressurized water nuclear reactors, said guide tubes displaying intense radiation-induced growth in the axial direction at the beg...  
WO/1997/040659A1
A fuel box for a nuclear fuel bundle for a boiling water reactor is manufactured by zirconium alloy plates. The plates have a composition such that the material after beta quenching and heat treatment will have a ductile, so-called baske...  
WO/1997/020601A1
A golf club (20) is made of a club shaft (22) and a club head (24). Either the club shaft (22) or the club head (24) is made at least in part of a bulk-solidifying amorphous metal. A preferred bulk-solidifying amorphous metal has a compo...  
WO/1997/019202A1
Disordered Multicomponent hydrogen storage material characterized by extraordinarily high storage capacity due to a high density of useable hydrogen storage sites (greater than 1023 defect sites/cc) and/or an extremely small crystallite ...  
WO/1996/038097A1
Dental and orthodontic articles comprising alloys of a material selected from the group consisting of Ti, Zr, Si, Mo, Co, Nb and Be. The alloys may further include at least one secondary alloying element selected from the group consistin...  
WO/1996/033518A1
A disordered electrochemical hydrogen storage alloy comprising: (Base Alloy)aCobMncFedSne where the Base Alloy comprises 0.1 to 60 atomic percent Ti, 0.1 to 40 atomic percent Zr, 0 to 60 atomic percent V, 0.1 to 57 atomic percent Ni, and...  
WO/1996/024140A1
A tube for forming a nuclear fuel assembly guide tube or sheath. The tube is made of an alloy containing 1.0-1.7 wt % of tin, 0.55-0.8 wt % of iron, 0.20-0.60 wt % total of chromium and/or vanadium, and 0.10-0.18 wt % of oxygen, carbon a...  
WO/1996/007764A1
The invention relates to a nuclear fuel element for pressurized-water reactors comprising a fuel cladding of a zirconium alloy composed of two parts. The inner part constitutes a supporting part of a conventional zirconium and the outer ...  
WO/1996/006956A1
A zirconium alloy including tin (Sn) in a range of greater than 0.005 wt.% to less than 1.0 wt.%, preferably with a lower limit greater than 0.1 wt.% to an upper limit of less than 0.7 wt.%, and most preferably with a lower limit of grea...  
WO/1996/004134A1
A reinforcement-containing metal-matrix composite material (20) is formed by dispersing pieces of reinforcement material (22) throughout a melt of a bulk-solidifying amorphous metal and solidifying the mixture at a sufficiently high rate...  
WO/1996/001492A1
There is described a method for creating and keeping a controlled atmosphere in a FED, essentially free of oxidizing gases and including hydrogen at a pressure comprised between 10-7 and 10-3 mbar, which comprises the step of arranging i...  
WO/1995/035395A1
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 st...  
WO/1995/018874A1
A zirconium alloy for nuclear fuel components such as cladding tubes, spacers, boxes, etc., with improved properties with respect to the absorption of hydrogen released during the corrosion, in combination with good strength and creep pr...  
WO/1995/001639A1
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 th...  
WO/1995/000672A1
The alloy of the present invention features controlled amounts of tin, nitrogen, and niobium and includes tin (Sn) in a range of greater than 0 to 1.50 wt.%, wherein 0.6 wt.% is typical. The alloy also has iron (Fe) in a range of greater...  
WO/1994/025395A1
A process for the removal of impurities from a stream of hydrogen, containing more easily removable impurities, like for instance COx, and more hardly removable impurities, mainly consisting of nitrogen and methane, wherein: A) said stre...  
WO/1994/023078A1
Alloys which form metallic glass upon cooling below the glass transition temperature at a rate appreciably less than 106 K/s comprise beryllium in the range of from 2 to 47 atomic percent and at least one early transition metal in the ra...  
WO1994023081A1
The zirconium-based material proposed according to the present invention contains the following components (proportions are given in wt %): niobium 0.5 to 1.5; tin 0.9 to 1.5; iron 0.3 to 0.6; chromium 0.005 to 0.2; carbon 0.005 to 0.04;...  
WO/1994/021834A1
A method for enhancing the water corrosion resistance of zirconium and zirconium alloys. According to the method, at least one metal element, e.g. 2-10 wt% of cerium, which can stabilise the quadratic phase of zirconia, is added to the z...  
WO/1994/016112A1
A stabilized alpha metal matrix provides an improved ductility, creep strength, and corrosion resistance against irradiation in a zirconium alloy containing on a weight percentage basis tin in a range of 0.4 to 1.0 percent and typically ...  
WO/1994/014990A1
A stabilized alpha metal matrix provides an improved ductility, creep strength, and corrosion resistance against irradiation in a zirconium alloy containing tin in a range of 0.45 to 0.75 wt. %, and typically 0.6 wt. %; iron in a range o...  
WO/1993/018520A1
A fuel rod has a cladding made of a thicker inner layer (4) to which is metallurgically bound a thinner outer layer (5). In view of the conditions prevalling inside the cladding tube and the mechanical properties of the whole cladding tu...  
WO/1993/017137A1
Zircaloy 2 and zircaloy 4 are tried and tested zirconium alloys in nuclear engineering with fixed concentration ranges for their components. The properties, especially corrosion resistance, mechanical stability and sensitivity to the pel...  
WO/1993/016205A1
A zirconium alloy which imparts good creep strength, while also providing favorable neutron cross section, improved corrosion resistance, low hydrogen uptake and good fabricability is described which contains vanadium in a range of from ...  
WO/1982/001899A1
An interchangeable and wettable solid cathode for the electrolysis of a melt electrolyte is comprised of at least an intermetal aluminum compound of the group IV A, V A or VI A of the periodic system of elements. The aluminum and titanum...  
JP5566877B2  

Matches 101 - 150 out of 1,334