Framatome Gmbh

Compagnie Europeenne Du Zirconium Cezus

Compagnie Generale Des Matieres Nucleaires

Framatome Anp Gmbh

Ugine Aciers

Compagnie Europeene Du Zirconium Cezus

Cezus

Cogema, Inc.

Pechiney

Zircotube

Societe En Nom Collectif Zircotube

Compagnie Europeenne Du Zirconium Dite Cezus

Compagnie Europeenne Du Zircomum Cezus

Daniel Charquet

Jean-Paul Mardon

Jean Senevat

Gerard Bunel

Jean Sevenat

Marc Perez

Marcel Armand

Max Dombre

Pierre Barberis

Jean Paul Mardon

Veronique Rebeyrolle

Charles Chauvel-Trepier

Marc Dall'Agnol

Yvon Millet

Jean-Pierre Gros

Rene Robin

The invention concerns an alloy containing equally 0.02 to 0.07% wt. % of the total iron, of chromium or vanadium, 0.8 to 1.3 wt. % of niobium, 100 ppm or less of tin, 1100 to 1700 ppm of oxygen, less than 100 ppm of carbon, 10 to 30 ppm of sulphur and less than 50 ppm of silicon.

Alloy and tube for nuclear fuel assembly and method for making same

The invention proposes a zirconium-based alloy also containing, by weight, apart from unavoidable impurities, from 0.02 to 1% of iron, from 0.8% to 2.3% of niobium, less than 2000 ppm of tin, less than 2000 ppm of oxygen, less than 80 ppm of carbon, from 5 to 35 ppm of sulphur and less than 0.25% in total of chromium and/or vanadium, the ratio R of the niobium content less 0.5% to the iron content, optionally supplemented by the chromium and/or vanadium content, being lower than 3.

Zirconium-based alloy and method for making a component for nuclear fuel assembly with same

The alloy contains, by weight, at least 95% zirconium and from 0.01 to 0.1% sulphur and, optionally, at least one element from the group consisting of the elements tin, iron, chromium, hafnium, niobium, nickel, oxygen and vanadium, the balance of the alloy consisting of inevitable impurities. The sulphur is present in the alloy in the dissolved state, thereby improving the creep strength and in the form of uniformly distributed fine precipitates, thereby improving the corrosion and hydriding resistance. The alloy may be heated by a solution annealing treatment in the &#x3b2; phase followed by a quench or by a soak at a temperature below 950&#xb0; C. in order to transform it into the &#x3b1; or &#x3b1;+&#x3b2; phase.

Zirconium-based alloy having a high resistance to corrosion and to hydriding by water and steam and process for the thermomechanical transformation of the alloy

Zirconium alloy highly resistant to corrosion and to sun burst by water and water vapor and method for thermomechanical transformation of the alloy

The invention proposes a zirconium-based alloy also containing, by weight, apart from unavoidable impurities, from 0.02 to 1% of iron having from 0.8% to 2.3% of 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 sulphur and from 0.01% to 0.25% in total of chromium and/or vanadium, the ratio R of the niobium content, less 0.5%, to the iron content, optionally supplemented by the chromium and/or vanadium content.

Zirconium based alloy and method for making a component for a nuclear fuel assembly with same

Tube for a nuclear fuel assembly, and method for making same

Zirconium alloy tube for a nuclear reactor fuel assembly, and method for

The alloy has a base composition similar to that of a zirconium alloy of known type used for the manufacture of an element intended for use in the core of a nuclear reactor, such as a cladding tube, a guide tube, or another structural element of a fuel assembly. In addition, the alloy contains sulphur in a proportion by weight of between 8 and 100 ppm and preferably between 8 and 30 ppm.

Zirconium-based alloy, manufacturing process, and use in a nuclear

A tube for constituting all or part of a cladding or guide tube for a fuel assembly is made from an alloy containing, by weight, 0.4% to 0.6% of tin, 0.5% to 0.8% of iron, 0.35% to 0.50% of vanadium, and 0.10% to 0.18% of oxygen, 100 ppm to 180 ppm of carbon and 50 ppm to 120 ppm of silicon. The alloy contains nothing else apart from zirconium and unavoidable impurities and it is completely recrystallized.

Zirconium-based alloy tube for a nuclear reactor fuel assembly

A method of manufacturing a tube suitable for use as sheath of a nuclear fuel rod zirconium based alloy. The alloy contains 0.18% to 0.25% iron, 0.07% to 0.13% chromium, 0.35% to 1.70% tin, all percentages by weight, 900 ppm to 2300 ppm oxygen, 80 ppm to 200 ppm carbon, and 50 ppm to 120 ppm silicon. A drawn blank is subjected to successive passes of metallurgical treatment and of heat treatment. The Fe/Cr ratio by weight in the alloy lies in the range 1.6 to 3. The heat treatment includes, after at least one rolling pass, a plurality of annealing passes under an inert atmosphere such that the sum .SIGMA.A is greater than 1.5.10.sup.-17, and advantageously in the range 2.10.sup.-17 to 2.10.sup.-16. The first rolling pass is performed on the tube coming from the drawing operation, without an intermediate annealing. .SIGMA.A designates the sum of the products of the times t (in hours) multiplied by the exponential of --Q/RT, where T is the temperature in K.

Sheathing tube for a nuclear fuel rod

A tube for constituting all or part of a cladding or guide tube for a fuel assembly is made from an alloy containing, by weight, 1.4% to 0.6% of tin, 0.5% to 0.8% of iron, 0.35% to 0.50% of vanadium, and 0.10% to 0.18% of oxygen, 100 ppm to 180 ppm of carbon and 50 ppm to 120 ppm of silicon. The alloy contains nothing else apart from zirconium and unavoidable impurities and it is completely recrystallized.

Zirconium-based alloy tube for a nuclear reactor fuel assembly and a

A process for the fabrication of zirconium alloy sheet specifically intended for the manufacture of structural elements for boiling water reactors, which includes the following steps:

Process for the production of zirconium alloy sheet metal having good

The method serves to manufacture tubes for constituting sheaths for nuclear fuel rods. A bar is made out of a zirconium-based alloy containing 50 ppm to 250 ppm iron, 0.8% to 1.3% by weight niobium, less than 1600 ppm oxygen, less than 200 ppm carbon, and less than 120 ppm silicon. The bar is heated to a temperature in the range 1000.degree. C. to 1200.degree. C. and is quenched in water. A blank is extruded after heating to a temperature in the range 600.degree. C. to 800.degree. C. and cold-rolled in at least four passes in order to obtain a tube, with intermediate heat treatment being performed between passes at temperatures in the range 560.degree. C. to 620.degree. C. A final heat treatment is performed at a temperature in the range 560.degree. C. to 620.degree. C., all of the heat treatments being performed under an inert atmosphere or a vacuum.

Method of manufacturing a tube for a nuclear fuel assembly, and tubes

A product having at least an exterior surface formed by a Zr alloy comprising the following addition elements (% by weight): Sn 0.40 to 1.70, Fe 0.05 to 0.25, Cr 0.03 to 0.16, Ni less than 0.08; the following maximum amounts of impurities (ppm): Al 75, B 0.5, Cd 0.5, C 270, Co 20, Cu 50, Hf 100, H.sub.2 25, Mg 20, Mn 50, Mo 50, N.sub.2 65, Si 120, Ti 50, W 10, U total 3.5; with the balance being O.sub.2 and Zr, wherein the Zr alloy has an Ni content which is greater than 70 ppm and less than 300 ppm.

Product externally alloyed with ZR, method for manufacture of same, and

Zircaloy 2 or 4 strip is heat treated in the beta range, followed by rapid cooling by passing the strip between a first and second roller pair, each roller pair having two oppositely disposed rollers gripping the strip. Each roller pair is connected to a source of an electric current so as to complete an electric circuit including the source, the roller pairs and the strip, which causes heating of the strip to the beta range. The strip is heated at a rate less than 40.degree. C./sec between 750.degree. and 1000.degree. C., held at 1000.degree.-1100.degree. for less than 2 minutes and cooled at a rate of at least 40.degree. C./sec between 1000.degree. C. and 600.degree. C.

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Albertville, France

Daniel Charquet