摘要:
A method of making a catalyst. The method comprises the step of leaching alloy particles. Preferably, the alloy particles are hydrogen storage alloy particles.
摘要:
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 β phase followed by a quench or by a soak at a temperature below 950° C. in order to transform it into the α or α+β phase.
摘要:
The present invention relates to high-purity zirconium or hafnium with minimal impurities, particularly where the content of alkali metal elements such as Na, K; radioactive elements such as U, Th; transitional metals or heavy metals or high melting point metal elements such as Fe, Ni, Co, Cr, Cu, Mo, Ta, V; and gas components such as C, O, etc. is extremely reduced, as well as to an inexpensive manufacturing method of such high-purity zirconium or hafnium, thereby reducing the impurities hindering the guarantee of the operational performance of semiconductors. The present invention further relates to an inexpensive and safe manufacturing method of high-purity zirconium or hafnium powder from hydrogenated high-purity zirconium or hafnium powder.
摘要:
Magnesium materials or components made of magnesium materials are protected against corrosion by a surface coating made of an alloy. The protective alloy coating contains a base alloy component A and at least one additive alloying component B. The base alloy component A is either titanium, or zirconium or magnesium. The alloying component B is selected from the following group: alkali metals, alkaline earth metals, rare-earth metals, yttrium, metals of the groups IIb, IIIa, IVa, and Va of the fourth or higher period of the periodic table of elements, and manganese.
摘要:
A corrosion and hydride resistant nuclear fuel rod having a highly corrosion resistant outer portion in which hydride precipitation is inhibited and an inner portion in which hydride precipitation is promoted.
摘要:
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 consisting of Ta, Cr, Al, V, Pd, Hf and Fe. The alloys preferably comprise a primary constituent in the range of about 30-85% by weight of the alloy, a secondary alloying component in the range of about 0.5-10% by weight, and the alloy has a modulus of elasticity in the range of about 5 million to 15 million psi.
摘要:
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 part a corrosion-resistant layer of zirconium with 0.65-0.95% Sn and 0.4-0.5% Fe. The difference in Sn content between the inner and outer parts must not exceed 0.7%. The cladding is finally heat-treated within the range 450 to 510.degree. C.
摘要:
A tube of zirconium-based alloy for constituting all or a portion of a cladding or guide tube for a nuclear fuel assembly. The tube is made of an alloy containing, by weight, 1.0-1.7% of tin, 0.55-0.80% of iron, 0.20-0.60% total of chromium and/or vanadium, and 0.10-0.18% of oxygen, with 50-200 ppm of carbon and 50-120 ppm of silicon. The alloy further contains only zirconium and unavoidable impurities, and it is completely recrystallized.
摘要:
A nuclear fuel rod for a pressurized water reactor having an elongated hollow metallic tubular cladding for containing nuclear fuel, the tubular cladding having an inner tubular layer of a zirconium alloy with alloying components of molybdenum and 3 to 6 weight percent bismuth, the balance zirconium.
摘要:
A method for manufacturing a delayed hydride cracking resistant zirconium ahoy (Zircaloy-2, Zircaloy-4, Zr-2.5% Nb, pure Zr, etc.) pressure tube includes the steps of making a seamless pressure tube having a diameter smaller than the final size by extrusion or drawing, and then expanding the tube at a temperature below 600.degree. C. by cross rolling.