Richard T Kimura, Age 651822 Davison Ave, Richland, WA 99352

Richard Kimura Phones & Addresses

1822 Davison Ave, Richland, WA 99352 (509) 943-6623

Naches, WA

Mattawa, WA

Bellingham, WA

1822 Davison Ave, Richland, WA 99354

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Position: Protective Service Occupations

Education

Degree: Associate degree or higher

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Medicine Doctors

Richard Y. Kimura

Specialties:
Orthopaedic Surgery
Work:
Richard Y Kimura MD
321 N Kuakini St STE 303, Honolulu, HI 96817
(808) 599-4456 (phone) (808) 599-4457 (fax)
Education:
Medical School
Tulane University School of Medicine
Graduated: 1969
Procedures:
Arthrocentesis, Hip/Femur Fractures and Dislocations, Knee Arthroscopy, Lower Arm/Elbow/Wrist Fractures and Dislocations
Conditions:
Fractures, Dislocations, Derangement, and Sprains, Internal Derangement of Knee Cartilage, Osteoarthritis, Rotator Cuff Syndrome and Allied Disorders
Languages:
English
Description:
Dr. Kimura graduated from the Tulane University School of Medicine in 1969. He works in Honolulu, HI and specializes in Orthopaedic Surgery. Dr. Kimura is affiliated with Kuakini Health System.

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Richard Kimura

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Us Patents

Apparatus And Method For Aiding In The Removal Of Enriched Uranium From Soils

US Patent:
7390934, Jun 24, 2008
Filed:
Jan 6, 2004
Appl. No.:
10/752751
Inventors:
Richard Thaddeus Kimura - Richland WA, US
Assignee:
Areva NP Inc. - Lynchburg VA
International Classification:
G21F 9/28
C01G 56/00
US Classification:
588 1, 423 3, 423 6, 423 10, 588 6, 588 7
Abstract:
A method and apparatus for removing uranium (IV) and uranium (VI) from sands and soils. The method and device assays a volume of soil and determines a presence and position of uranium enrichment. A concentration of uranium enrichment is determined, and compared to a threshold concentration. The volume of soil is processed and transported to a coarse screen, deck screen and classified in a classifier. In the classifier, the volume of soil is separated into a washed and fines fraction, assayed and transported to a uranium recovery facility, then transported to a silicon removal process and subsequent ammonia and metals removal processes.

Ultrasonic Counter-Current Screw Extractor For Uranium Recovery And Process Therefore

US Patent:
7527772, May 5, 2009
Filed:
Jul 1, 2004
Appl. No.:
10/883073
Inventors:
Richard Thaddeus Kimura - Richland WA, US
Assignee:
AREVA NP Inc. - Lynchburg VA
International Classification:
C22B 9/00
US Classification:
423 20, 423 4, 423 8, 423 9, 423 10, 366127
Abstract:
An apparatus and method to remove uranium from a body of material wherein the method includes the steps of depositing the body of solid material in an ultrasonic extractor and depositing an amount of acid in the ultrasonic extractor. The method also provides for the steps of heating a jacket of the ultrasonic extractor, transporting the body of solid material in the ultrasonic extractor and the amount of acid such that the body of solid material and the acid contact each other inside the heated ultrasonic extractor while the ultrasonic extractor provides ultrasonic energy to both the body of solid material and the amount of acid, wherein the amount of acid strips uranium from the body of solid material. The method further provides for collecting the amount of acid and the body of solid material in the ultrasonic extractor in different positions, transporting the amount of acid with the stripped uranium to an extraction mixer settler, and settling uranium product from the extraction mixer settler.

Ultrasonic Counter-Current Screw Extractor For Uranium Recovery

US Patent:
7780921, Aug 24, 2010
Filed:
Mar 27, 2009
Appl. No.:
12/412573
Inventors:
Richard Thaddeus Kimura - Richland WA, US
Assignee:
Areva NP Inc. - Lynchburg VA
International Classification:
G21C 1/00
B01F 11/02
US Classification:
422159, 366127, 423 2, 423 3, 423 4, 423 8, 423 9, 423 10, 423 11, 423 18, 423 20, 266168, 266171, 266176, 266177, 266183
Abstract:
An apparatus for the removal of uranium from a body of material is provided. The apparatus has at least one ultrasonic extractor, having a bottom and a top. The at least one ultrasonic extractor is configured to accept solids at the bottom and acid at the top, and has a mixing screw and at least one source of ultrasonic energy. The mixing screw is configured to transport the solids in a direction countercurrent to the acid in the at least one ultrasonic extractor; and the source of ultrasonic energy is configured to impart ultrasonic energy into the solids and the acid, as the solids and the acid traverse the at least one ultrasonic extractor countercurrently.

Segmented Reactors For Capacity And Enrichment Changes In Conversion Of Uranium Hexafluoride To Uranium Dioxide

US Patent:
8329109, Dec 11, 2012
Filed:
Nov 10, 2010
Appl. No.:
12/943704
Inventors:
Richard Thaddeus Kimura - Richland WA, US
Andrew Landon - Richland WA, US
Clifford Yeager - Richland WA, US
Assignee:
Areva NP - Lynchburg VA
International Classification:
G21C 1/00
B01J 8/18
US Classification:
422159, 422139, 422141, 422142, 423261
Abstract:
A dry conversion reactor for converting uranium hexafluoride to uranium dioxide, the dry conversion reactor including a gas-phase reaction segment and a fluidized bed segment, wherein at least one of the gas-phase reaction segment and the fluidized bed segment is a replaceable segment. A method for operating a dry conversion reactor utilizing a uranium hexafluoride to uranium dioxide conversion process, the method including replacing at least one conversion reactor segment.

Process For Selective Recovery Of Uranium From Sludge

US Patent:
6010671, Jan 4, 2000
Filed:
May 22, 1998
Appl. No.:
9/084025
Inventors:
Richard T. Kimura - Richland WA
Assignee:
Siemens Power Corporation - Richland WA
International Classification:
C01G 5600
C22B 6000
US Classification:
423 3
Abstract:
A process for recovering uranium from a waste sludge involves treating the sludge with a non-reactive, non-absorptive cellulose filtration media, adding an oxidant and heating the mixture to dissolve any uranium present. The mixture is passed through a filtration device precoated with the same filtration media, where the solids are captured while the dissolved uranium passes through as part of the filtrate, for recovery.

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