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Arnold S Kitzes Deceased9 Hearthstone Dr, Pittsburgh, PA 15235

Arnold Kitzes Phones & Addresses

9 Hearthstone Dr, Penn Hills, PA 15235    412-2437391    412-2437401   

2740 Mount Royal Rd, Squirrel Hill, PA 15217    412-5215209   

Pittsburgh, PA   

3890 Bigelow Blvd APT 443, Pittsburgh, PA 15213   

Work

Position: Food Preparation and Serving Related Occupations

Education

Degree: Graduate or professional degree

Emails

Mentions for Arnold S Kitzes

Career records & work history

License Records

Arnold Stanley Kitzes

Address:
Pittsburgh, PA 15217
Licenses:
License #: PE010011E - Expired
Category: Engineers
Type: Professional Engineer

Publications & IP owners

Us Patents

Process For Uniting Sleeve Members By Brazing

US Patent:
4572938, Feb 25, 1986
Filed:
Jan 16, 1984
Appl. No.:
6/571215
Inventors:
John M. Driggers - Penn Hills PA
Thomas J. Saska - Lower Burrell PA
Arnold S. Kitzes - Pittsburgh PA
Assignee:
Westinghouse Electric Corp. - Pittsburgh PA
International Classification:
B23K 102
B23K 104
US Classification:
219 85BM
Abstract:
Small portable electrical resistance heated radiant heating unit useful for insertion in tube bores to effect localized high temperature heating. Useful for the internal heating of tubes and tube/sleeve assemblies in steam generators, for brazing, stress relieving, and other applications. Has a machined mandrel of boron nitride and electrical resistance wire leads that have reduced electrical resistance for reduced heat generation by the leads. The leads preferably are braided, to permit the use of cramped connectors.

Volume Reduction Of Spent Radioactive Ion-Exchange Material

US Patent:
4053432, Oct 11, 1977
Filed:
Mar 2, 1976
Appl. No.:
5/663035
Inventors:
Erich W. Tiepel - Export PA
Christopher K. Wu - Wilkins PA
Arnold S. Kitzes - Pittsburgh PA
Assignee:
Westinghouse Electric Corporation - Pittsburgh PA
International Classification:
G21F 932
US Classification:
2523011W
Abstract:
A process for reducing the volume of spent organic radioactive ion-exchange material which has been used for conditioning water circulated through a nuclear reactor. The spent radioactive ion-exchange material is removed from the reactor system and inserted into a dryer, where the residual free water and some of the intrinsic water in the ion-exchange material is removed so that the ion-exchange material has a moisture content less than 50% by weight. The dried ion-exchange material is then inserted into a fluid bed reactor, a carrier gas is inserted into the reactor and fluidizes the ion-exchange material, and the ion-exchange material is heated. The heating thermally decomposes the ion-exchange material, producing an effluent gas, which contains the volatile decomposition products. The carrier gas and the effluent gas are removed from the fluid bed reactor. After the thermal decomposition, or pyrolysis, is completed, the insertion of the carrier gas into the reactor is stopped and an oxygen-containing gas is inserted into the reactor.

Volume Reduction Of Spent Radioactive Ion Exchange Resin

US Patent:
4008171, Feb 15, 1977
Filed:
Sep 10, 1973
Appl. No.:
5/395803
Inventors:
Erich W. Tiepel - Export PA
Pang K. Lee - Pittsburgh PA
Arnold S. Kitzes - Pittsburgh PA
Donald L. Grover - McMurray PA
Assignee:
Westinghouse Electric Corporation - Pittsburgh PA
International Classification:
G21F 930
US Classification:
2523011W
Abstract:
A process for reducing the volume of spent radioactive ion exchange resins which have been used for conditioning water circulated through a nuclear reactor. The spent resins are discharged from the reactor system as radioactive wastes to a spent resin storage tank in the form of a slurry. The slurry is first vacuum dewatered to remove the free water and then the intrinsic water in the wet resin beads is removed by drying in a vacuum fluidized bed chamber utilizing superheated steam which also acts to fluidize the bed. Further drying is accomplished by spraying the partially dried resin and superheated steam through a steam injected two-fluid nozzle for further extraction of intrinsic water from the resins. The steam is discharged to a condenser and the dried resins to an evacuated disposal drum. Approximate 4:1 volume reductions from the resin-water slurry to the dried resin is obtainable by practicing the process.

Process And Apparatus For The Volume Reduction Of Pwr Liquid Wastes

US Patent:
4444680, Apr 24, 1984
Filed:
Jun 26, 1981
Appl. No.:
6/277579
Inventors:
Arnold S. Kitzes - Pittsburgh PA
Erich W. Tiepel - Littleton CO
Assignee:
Westinghouse Electric Corp. - Pittsburgh PA
International Classification:
G21F 908
US Classification:
252632
Abstract:
An apparatus for the volume reduction of radioactive liquid waste solutions such as evaporator waste bottoms containing boric acid or sodium sulfate and trace quantities of radioactivity through a vacuum evaporative cooling crystallization process or an evaporative crystallization process. A crystallization unit has an internal baffle which separates the center portion of the unit into a quiescent zone where crystallization can be effected and an inner chamber into which the liquid waste is tangentially introduced. The waste is circulated from the bottom of the crystallization unit through a heat exchanger which adjusts the temperature of the liquid waste and maintains the temperature within a predetermined range. The vacuum draws off a portion of the solvent in the solution. Upon the crystallization of the liquid waste solution to a degree which renders a solid-liquid slurry, the slurry is removed from the apparatus for further treatment.

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