Westinghouse Electric Corporation

Michael C Skriba

David C Grant

Edward Jean Lahoda

John Bartko

Thomas V Congedo

Steven H Peterson

Eugene E Smeltzer

Edward F Sverdrup

Robert E Witkowski

Arthur L Wolfe

William D Partlow

Thomas S Snyder

David F McLaughlin

Alexander P Murray

Ernest D Lee

Clifton G Slater

Keith K McDaniel

David L Ayers

Lawrence F Becker, Jr

Terry Wright

The concentrations of residual heavy metal contaminants in the particulate material in a slurry produced in a particulate material washing process are monitored on-line and can be used to control the washing process. In alternative embodiments of the invention, x-rays, thermal neutrons or laser beams are directed at the slurry as it flows through a flow cell to induce emission of secondary x-rays, gamma rays or light, respectively, characteristic of the heavy metal contaminants and constituents representative of the solids contents of the slurry. These characteristic energies are measured and used to determine the concentration in ppm of the residual heavy metal contaminants in the particulate material within the slurry.

System and method for on-line monitoring and control of heavy metal

A process for removing metal from a solid material includes the steps of admixing the metal containing solid (10) with an aqueous liquid (26) and particles of ion exchange material (28) having a strong affinity for metal in a mixer (24), to form a slurry, allowing the slurry materials to interact, and removing the ion exchange material loaded with metal (32) from the solid.

Method of restoring contaminated solids using ion exchange powder contact

The thermal neutron capture cross-section of zirconium may be altered by altering its natural isotope distribution through a steady state chromatographic separation of these isotopes using an anion exchange resin as the stationary phase of the chromatographic column. Zirconium is dissolved in a very strong acid which causes the formation of a zirconium anion, such as the ZrOCl.sub.4.sup.-2 anion formed in six normal hydrochloric acid, and eluted off the column with a weaker acid. Distinct elution volumes representative of each isotope are collected. In a preferred embodiment, the process also separates the zirconium from hafnium and the other impurities normally present in the product obtained by chlorinating zircon sand and utilizes a continuous annular chromatograph.

Continuous anion exchange chromatography for the separation of zirconium

Waste material containing hazardous or radio-active species is treated by: separating a portion of the waste material and identifying the particle size range of the severely contaminated fraction by use of a sieving apparatus (6) and a contamination detection apparatus (8); passing the waste material (15) near a contamination detection apparatus (12) to identify the waste material that is contaminated and segregate that material by a diverter (17) to provide contaminated portion (19); passing the contaminated portion (19) into a fluidized bed apparatus (16) where an aqueous leaching solution (21), effective to leach soluble, contamination species, contacts the contaminated material at an upward velocity effective to remove the particle size range that is determined to contain the severely contaminated fraction of the waste material, to provide a severely contaminated effluent slurry (24); and removing the leach solution from the slurry in a dewatering apparatus (26) to provide a solution (27) containing solubilized, severely contaminated species.

Contaminated soil restoration method

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 an appropriate supercritical fluid solvent, contacting the porous support with the supercritical fluid solution of the catalytic metal salt to impregnate the porous support with the solution so that the catalytic metal salt may be adsorbed on the surfaces of the support, and removing the supercritical fluid solvent by reducing the pressure or increasing the temperature to change the supercritical fluid from the supercritical fluid phase to the gas phase, which may then be recycled for further use. The insoluble catalytic metal salt is deposited in the form of a film on the surfaces of the support. The catalytic metal salt-containing porous support may then be processed conventionally to produce a substantially pure, high activity supported metal catalyst.

Catalyst preparation using supercritical solvent

For removal of the contaminant deposits from a surface such as a tube sheet of a vertical tube heat exchanger, as in a nuclear steam generator, having plural spaced heat exchange tubes connected to the tube sheet, a lance is radially moved along the tube sheet between parallel rows of tubes. The lance carries a nozzle for ejecting a stream of high pressure cleaning fluid toward the sludge deposits, the nozzle acting cyclically to sweep the stream throughout a range of directions centered about the nozzle axis. The nozzle may include diverting streams for deflecting the cleaning fluid stream, with the diverting streams either being generated by a fluidic oscillator or being fed back from the outlet portion of the nozzle. Alternatively, pivoting vane means may be provided in the nozzle to divert the cleaning fluid stream.

Method and apparatus for providing oscillating contaminant-removal stream

A process is described for reducing the volume of spent ion exchange resins containing radioactive contaminants, and a filter aid having groups reactive with the functional groups of the resins. Spent ion exchange resin and the filter aid are dewatered, then subject to a pressure of about 2000 psi in conjunction with 250.degree. C. heat to reduce the volume occupied by the resin by up to a factor of 5 and impart rewet stability.

Ion exchange resin volume reduction

Disclosed is an improved process for oxidizing chromium in deposits in the cooling system of a nuclear reactor using a solution of ozone. The improvement consists of adding to the solution about 0.01 to about 0.5% of a water-soluble cerium IV compound, about 0.1 to about 0.5% of a water-soluble aromatic compound having at least one ketone group on an aromatic ring, or adding both. Also disclosed is the composition of water, ozone, the cerium IV compound and the aromatic compound. Also disclosed is a process for decontaminating the cooling system of nuclear reactors by adding a decontamination composition to the coolant, circulating the coolant between the cooling system and a cation exchange resin, removing the decontamination composition by passing it through an anion exchange resin, adjusting the temperature to 40.degree. to about 100.degree. C., adding the ozone oxidation composition, circulating the coolant through the cooling system, raising the temperature to at least about 100.degree. C., passing the coolant through an anion exchange resin or a mixed resin, adjusting the temperature to about 60.degree. to 100.degree. C. and repeating the addition of the decontamination composition and its removal.

Ozone oxidation of deposits in cooling systems of nuclear reactors

Disclosed is a method for rapidly forming a solid monolith of an aqueous mixture of an ion exchange resin and boric acid. A fouling agent and sufficient basic accelerator to neutralize the mixture are added. Cement is then added which hardens in a few hours. Also disclosed is a composition of the ion exchange resin, boric acid, water, a fouling agent, a basic accelerator, and cement.

Growing community of inventors

Newport Beach, CA, United States of America

Michael C Skriba