Abstract: It has been found that modifying standard Zircaloy alloy processing techniques by limiting the working and annealing temperatures utilized after conventional beta treatment results in Zircaloy alloy product having superior high temperature steam corrosion resistance.

Abstract: A spacer for supporting a plurality of fuel rods forming a nuclear fuel assembly. The spacer comprises a peripheral band surrounding a bundle of the fuel rods and a plurality of spacer framework units, each holding therein one fuel rod. The spacer framework units are welded or brazed to the peripheral band so as to be arranged inside the peripheral band. Spring members are integrally formed on each of the spacer framework units. The spacer framework units, the spring members and the peripheral band are made of a zirconium alloy containing 5-25% by weight niobium and 0.1-1% by weight chromium and/or iron.

Abstract: An austenitic stainless steel alloy is disclosed, having excellent fast neutron irradiation swelling resistance and good post irradiation ductility, making it especially useful for liquid metal fast breeder reactor applications. The alloy contains: about 0.04 to 0.09 wt. % carbon; about 1.5 to 2.5 wt. % manganese; about 0.5 to 1.6 wt. % silicon; about 0.030 to 0.08 wt. % phosphorus; about 13.3 to 16.5 wt. % chromium; about 13.7 to 16.0 wt. % nickel; about 1.0 to 3.0 wt. % molybdenum; and about 0.10 to 0.35 wt. % titanium.

Abstract: An alloy for use in an environment exposed to neutron rays consists principally of Cr-Ni austenite stainless steel containing nitrogen in an amount exceeding the amount of an impurity and having principally an austenite structure. The alloy is used for reactor core members such as a core shroud, core supporters, control rods, etc. which are exposed to the neutron radiation but prevented from being embrittled by the radiation.

Abstract: A method and alloys for fabricating wrought components of a high-temperature gas-cooled reactor are disclosed. These wrought, nickel-based alloys, which exhibit strength and excellent resistance to carburization at elevated temperatures, include aluminum and titanium in amounts and ratios to promote the growth of carburization resistant films while preserving the wrought character of the alloys. These alloys also include substantial amounts of molybdenum and/or tungsten as solid-solution strengtheners. Chromium may be included in concentrations less than 10% to assist in fabrication. Minor amounts of carbon and one or more carbide-forming metals also contribute to high-temperature strength.

Abstract: This invention describes a composition for an austenitic stainless steel which has been found to exhibit improved high temperature stress rupture properties. The composition of this alloy is about (in wt. %): 12.5 to 14.5 Cr; 14.5 to 16.5 Ni; 1.5 to 2.5 Mo; 1.5 to 2.5 Mn; 0.1 to 0.4 Ti; 0.02 to 0.08 C; 0.5 to 1.0 Si; 0.01 maximum, N; 0.02 to 0.08 P; 0.002 to 0.008 B; 0.004-0.010 S; 0.02-0.05 Nb; 0.01-0.05 V; 0.005-0.02 Ta; 0.02-0.05 Al; 0.01-0.04 Cu; 0.02-0.05 Co; 0.03 maximum, As; 0.01 maximum, O; 0.01 maximum, Zr; and with the balance of the alloy being essentially iron. The carbon content of the alloy is adjusted such that wt. % Ti/(wt. % C+wt. % N) is between 4 and 6, and most preferably about 5. In addition the sum of the wt. % P+wt. % B+wt. % S is at least 0.03 wt. %. This alloy is believed to be particularly well suited for use as fast breeder reactor fuel element cladding.

Abstract: In-pile parts for a nuclear reactor made of alloy consisting essentially of by weight 0.01-0.2% C, 10-21% Cr, 1-4% Ti, 0.3-2% Nb, 0.1-2% Al and the balance Ni wherein Ti content being higher than Nb content, said alloy having the microstructure of chromium carbides precipitated in the grain boundaries and a .gamma.' phase precipitated in the grains with the matrix thereof being austenite in microstructure.

Abstract: The invention relates to a nickel/iron casting alloy, containing no cobalt, exhibiting high strength at elevated temperatures accompanied by insensitivity to thermal fatigue, and possessing microstructural constituents which are thermodynamically highly stable. The alloy exhibits high hardness at elevated temperatures, outstanding resistance to oxidation, corrosion and wear, as well as good welding properties. The alloy is particularly suitable as a material for nuclear reactor components, and is composed of1.1 to 1.6% of carbon0.5 to 1.5% of silicon0.01 to 0.2% of manganese22 to 26% of chromium12.5 to 14.5% of molybdenum0.2 to 0.8% of niobium (columbium)35 to 40% of nickelless than 0.01% of boronless than 0.002% of tantalum and18 to 26% of iron, to make up 100%.

Abstract: A sliding mechanism comprising two members maintained in sliding contact with each other, wherein one of the members (which may be a pin) is formed of an alloy consisting essentially of, by weight, less than 0.3% carbon, 7-40% nickel, 15-28% chromium, 2-8% silicon, 3-12% manganese and the balance essentially iron, and the other member (which may be a roller) is formed of an alloy consisting essentially of, by weight, less than 0.5% carbon, 13-22% chromium, less than 2% silicon, less than 2% manganese, 3-10% molybdenum, 10% of at least one of titanium and aluminum and the balance essentially nickel, the two members having a difference in Vickers hardness of below 200 at their contact surfaces. The sliding mechanism has particualr utility as means for guiding a control rod of a nuclear reactor by means of pins and rollers.

Abstract: A fuel assembly for a nuclear reactor comprises a 5.times.5 array of guide tubes in a generally 20.times.20 array of fuel elements. The guide tubes are arranged to accommodate either control rods or water displacer rods. The fuel assembly also comprises a plurality of Inconel and Zircaloy grids arranged to provide stability of the fuel elements and guide tubes while allowing the flow of reactor coolant therebetween.

Abstract: Ductile long range ordered alloys having high critical ordering temperatures exist in the (V,M)(Fe,Ni,Co).sub.3 system having the composition comprising by weight 20.6%-22.6% V, 14-50% Fe, 0-64% Co, and 0-40% Ni, and 0.4-1.4% M, where M is a metal selected from the group consisting of Ti, Zr, Hf, and their mixtures. These modified alloys have an electron density no greater than 8.00 and exhibit marked increases at elevated temperature in ductility and other mechanical properties over previously known ordered alloys.

Abstract: Zirconium-base alloy channels, fuel cladding tubes and other nuclear reactor structural components having unique resistance to accelerated pustular corrosion in the boiling water reactor environment are produced by a sequence of heat treatments causing segregation of intermetallic particulate precipitate phase in two dimensional arrays of particles of diameter from 100 to 400 Angstroms located along grain boundaries and sub-grain boundaries throughout the alloy body.

Abstract: An alloy which is significantly resistant to swelling and irradiation induced hardening when exposed to a high-neutron flux at high temperatures is obtained by alloying from 3 to 7 weight percent of molybdenum and from 0.8 to 1.2 weight percent of zirconium with niobium.

Abstract: The invention is concerned with providing substrates with coatings obtainable from sols, for example to protect the substrate (such as in nuclear reactors or hydrocarbon cracking plant) or to provide a carrier for catalytically active material.Hitherto, coatings obtained from sols have had a high porosity and high surface area so that they have not been entirely satisfactory for the above applications.In the invention, dense, low-porosity coatings are provided by contacting the substrate with a sol of refractory material (e.g. CeO.sub.2 or SiO.sub.2) convertible to a gel of density at least 40% of the theoretical density of the refractory material, and converting the sol to the gel. Optionally, the gel may be converted to a ceramic coating by firing.