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Inventor:
McLaughlin; David F.
Address:
Oakmont, PA
No. of patents:
16
Patents:












Patent Number Title Of Patent Date Issued
7887638 Removal of niobium second phase particle deposits from pickled zirconium-niobium alloys February 15, 2011
The present invention relates generally to a process and chemical composition for the removal of adherent niobium-rich second-phase particles (SPPs) from pickled niobium-containing zirconium alloys which includes applying to the alloy surface a chemical composition comprising alkalin
7556696 Removal of niobium second phase particle deposits from pickled zirconium-niobium alloys July 7, 2009
The present invention relates generally to a process and chemical composition for the removal of adherent niobium-rich second-phase particles (SPPs) from pickled niobium-containing zirconium alloys which includes applying to the alloy surface a chemical composition comprising alkalin
7468106 Removal of niobium second phase particle deposits from pickled zirconium-niobium alloys December 23, 2008
The present invention provides a method for removing niobium-rich second-phase-particle (SPP) deposits from zirconium-niobium alloy components. The method comprises washing a freshly pickled and rinsed zirconium-niobium alloy component with an acidified oxalic acid or ammonium oxalat
6719952 Fluidized bed reaction design April 13, 2004
A fluidized bed reactor (10) for chemically transforming reactants to generate a desired product, having a hollow, elongated, vertically oriented reactor housing (12) for confining the reaction and an unobstructed collection path (18) below the reaction zone for funneling the residue
6252923 In-situ self-powered monitoring of stored spent nuclear fuel June 26, 2001
Detectors are used to monitor the status of spent nuclear fuel storage containers non-invasively while they remain in storage casks. The detectors measure neutron flux and .gamma.-ray flux and may also measure temperature variations of the spent nuclear fuel. The measurements can be
5637127 Plasma vitrification of waste materials June 10, 1997
This invention provides a process wherein hazardous or radioactive wastes in the form of liquids, slurries, or finely divided solids are mixed with finely divided glassformers (silica, alumina, soda, etc.) and injected directly into the plume of a non-transferred arc plasma torch. The
5539788 Prompt gamma neutron activation analysis system July 23, 1996
A system for determining depth profiles of concentrations of hazardous elements in soils comprises a neutron source for generating neutrons of a first energy level and irradiating a volume of soil with the neutrons. Nuclear reactions are effected within the soil and gamma radiation is
4923577 Electrochemical-metallothermic reduction of zirconium in molten salt solutions May 8, 1990
This is a method of reducing zirconium chloride to a metal product by introducing zirconium chloride into a molten salt bath containing at least one alkali metal chloride and at least one alkaline earth metal chloride; and electrochemically reducing alkaline earth metal chloride to a met
4916108 Catalyst preparation using supercritical solvent April 10, 1990
A process for producing supported metal catalysts having increased catalytic activity is provided. This process includes the steps of forming a high surface area porous support of a suitable porous material such as alumina or zirconia, dissolving a salt of a selected catalytic metal in a
4913778 Molten salt scrubbing of zirconium or hafnium tetrachloride April 3, 1990
Removal of aluminum and iron impurities is accomplished using an absorbing column containing potassium or sodium chloride, producing an aluminum and iron chloride-rich bottoms product and purified Zr(Hf)Cl.sub.4 vapor at the top of the column. This invention is a continuous process for r
4874475 Molten salt extractive distillation process for zirconium-hafnium separation October 17, 1989
Improvements are described to a process in which the extractive distillation separation of zirconium or hafnium may be accomplished using mixtures of fused alkali metal or alkali metal and alkaline earth chlorides as the solvent. The solvent composition is adjusted to provide a low-m
4865696 Recovery of metal chlorides from their complexes by molten salt displacement September 12, 1989
This is a process for removing phosphorus oxychloride from a complex of zirconium or hafnium chloride and phosphorus oxychloride utilizing a lithium-potassium chloride molten salt absorber vessel displacing phosphorous oxychloride from the complex, with a condenser which has the comp
4865694 Electrochemical decomposition of complexes of zirconium or hafnium September 12, 1989
This is an improved method for separating hafnium from zirconium of the type where a complex of zirconium and hafnium chlorides and phosphorus oxychloride is prepared from zirconium-hafnium chloride and the complex is introduced into a distillation column, with the improvement comprising
4865693 Preparation of complexes of zirconium and hafnium tetrachlorides with phosphorus oxychloride September 12, 1989
This is a zirconium-hafnium separation process utilizing a complex of zirconium-hafnium chlorides and phosphorus oxychloride. The complex is introduced into a distillation column and a hafnium chloride enriched stream is taken from the top of the column and a zirconium chloride enric
4749448 Zirconium and hafnium tetrachloride separation by extractive distillation with molten zinc chlor June 7, 1988
This is a molten salt extractive distillation process for separating hafnium from zirconium. It utilizes at least principally a ZnCl.sub.2 --Ca/MgCl.sub.2 molten salt solvent, and preferably ZnCl.sub.2 --Ca/MgCl.sub.2 in a near 95-15 mixture. The extraction column is preferably run a
4737244 Zirconium and hafnium tetrachloride separation by extractive distillation with molten zinc chlor April 12, 1988
This is a molten salt extractive distillation process for separating hafnium from zirconium. It utilizes at least principally a ZnCl.sub.2 -PbCl.sub.2 molten salt solvent, and preferably ZnCl.sub.2 -PbCl.sub.2 in a near eutectic or eutectic mixture. The extraction column is preferably










 
 
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