Thomas S. Snyder - Oakmont PA Alexander P. Murray - Murrysville PA
Assignee:
Westinghouse Electric Corp. - Pittsburgh PA
International Classification:
C25F 100 C25F 700
US Classification:
204140
Abstract:
Both a method and apparatus for electrolytically removing radioactive metal ions from a decontamination solution to regenerate the solution and prepare the ions for disposal as disclosed herein. At least the cathodic portion of the electrode used in the electrolysis is formed from a combustible material, such as a semi-fluidized bed of graphite particles. In the method of the invention, the decontamination solution is passed in intimate contact with the graphite particles forming the cathodic portion of the electrode as an electric potential is applied to the electrode. As a result of the electric potential, the metal ions are detached from the chelate in the decontamination solution and deposited onto the graphite particles of the cathodic portion of the electrode. After the electrode becomes spent, it is incinerated in order to reduce the volume of the resulting radioactive ash. The gases produced from the incineration are scrubbed with a scrubbing liquid to remove radioactive particles therefrom.
Method Of Decontaminating Radioactive Metal Surfaces
Alexander P. Murray - Murrysville PA Clifton G. Slater - Wilkinsburg PA
Assignee:
Westinghouse Electric Corp. - Pittsburgh PA
International Classification:
G21F 900
US Classification:
252626
Abstract:
Disclosed is a method of decontaminating metal surfaces contaminated with a radioactive deposit by passing over the coating an aqueous solution of a water soluble condensation reaction product of (1) a hydrazine compound having the general formula ##STR1## where each R group is independently selected from hydrogen and alkyl to C. sub. 4 and (2) a water soluble aliphatic polycarboxylic acid. The method includes the additional last steps of passing an aqueous oxidizing solution over the deposit followed by passing a decontamination solution over the deposit a second time. The solution is circulated through a cationic exchange column which can be preloaded with hydrazine ion. The decontamination solution can be decomposed by the addition of an oxidant to form nitrogen, carbon dioxide, and water.
Alexander P. Murray - Murrysville PA Thomas S. Snyder - Wilkins Township, Allegheny County PA
Assignee:
Westinghouse Electric Corp. - Pittsburgh PA
International Classification:
C25F 302
US Classification:
20412995
Abstract:
Disclosed is a method of decontaminating metal surfaces having a radioactive coating thereon where the coating contains metal ions. An aqueous decontamination solution containing at least one chelate is passed over the coating to solubilize the metals. The decontamination solution is then passed through a porous direct current electrode to reduce the metal ions in the solution and the decontamination solution is again passed over the coating. Also disclosed is an apparatus for decontaiminating metal surfaces coated with radioactive substances. The apparatus consists of a container means for holding an aqueous decontamination solution where the solution contains a chelate, a porous cathode through which the aqueous decontamination solution is passed, and means for circulating the aqueous decontamination solution between the container means, the porous cathode, and the metal surfaces.
Decontamination Of Metal Surfaces In Nuclear Power Reactors
Alexander P. Murray - Murrysville PA Sharon L. Weisberg - Pittsburgh PA Lawrence F. Becker - N. Huntingdon PA
Assignee:
Westinghouse Electric Corp. - Pittsburgh PA
International Classification:
G21F 900 C23G 102
US Classification:
252626
Abstract:
A method for decontaminating metal surfaces having radioactive oxide deposits thereon is disclosed which comprises preparing a decontamination solution having a pH of about 1. 5 to about 4 comprising water, about 0. 02 to about 0. 5% of a water soluble organic acid which has an equilibrium constant in a complex with ferric ion of at least about 10. sup. 9 and which is capable of producing a pH of about 2 to about 3 in water, and about 0. 01 to about 0. 4% of a chelate in free acid form which has an equilibrium constant in a complex with ferric ion of about 10. sup. 15 to about 10. sup. 19 and which is at least 0. 4% soluble at 40. degree. C. in water having a pH of about 2 to about 3. An apparatus for performing the above method is disclosed.
Ozone Oxidation Of Deposits In Cooling Systems Of Nuclear Reactors
Alexander P. Murray - Murrysville PA Lawrence F. Becker - North Huntingdon PA Clifton G. Slater - Wilkinsburg PA Michael C. Skriba - Plum Borough PA
Assignee:
Westinghouse Electric Corp. - Pittsburgh PA
International Classification:
G23G 100 G21F 900
US Classification:
134 2
Abstract:
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.
Hypohalite Oxidation In Decontaminating Nuclear Reactors
Disclosed is an oxidizing composition of water, about 0. 1 to saturation of an alkali metal hypohalite, and sufficient alkali metal hydroxide to raise the pH of the solution to at least about 12. A method of decontaminating metal surfaces having a coating thereon which contains radioactive substances is also disclosed. The composition is passed over the coating at a temperature of about 50. degree. to about 120. degree. C. followed by passing a decontamination solution over the coating.
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Date: Feb 01, 2025
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