Robert T Jubin

US Patent:

20120213658, Aug 23, 2012

Filed:

Feb 22, 2011

Appl. No.:

13/031982

Inventors:

W. Scott Aaron - Clinton TN, US
Emory D. Collins - Knoxville TN, US
Guillermo D. DelCul - Powell TN, US
Robert T. Jubin - Powell TN, US
Raymond J. Vedder - Knoxville TN, US

Assignee:

UT-BATTELLE, LLC - Oak Ridge TN

International Classification:

B22F 1/00
B22F 3/02

US Classification:

419 19, 419 66, 75230

Abstract:

A system and method for stabilizing fission products in a cermet for long term storage. The method includes forming a metal oxide precipitate, combining the metal oxide precipitate with an undissolved solid, and densifying the combined metal oxide precipitate and the undissolved solid to provide a cermet having a ceramic dispersed phase and a metallic matrix phase, wherein the metallic matrix phase includes metallic content from the undissolved solid. The undissolved solid can include fission product metals from the reprocessing of irradiated nuclear fuel. The cermet waste loading can be greater than approximately 30 percent, reducing waste volume by 50 percent or more when compared to baseline glassified articles.

US Patent:

49254413, May 15, 1990

Filed:

Jun 13, 1989

Appl. No.:

7/365636

Inventors:

Robert T. Jubin - Powell TN

Assignee:

The United States of America as represented by the United States
Department of Energy - Washington DC

International Classification:

B04B 500

US Classification:

494 32

Abstract:

A cascade formed of a plurality of centrifugal contactors useful for countercurrent solvent extraction processes such as utilizable for the reprocessing of nuclear reactor fuels is modified to permit operation in the event one or both end stages of the cascade become inoperative. Weir assemblies are connected to each of the two end stages by suitable conduits for separating liquids discharged from an inoperative end stage based upon the weight of the liquid phases uses in the solvent extraction process. The weir assembly at one end stage is constructed to separate and discharge the heaviest liquid phase while the weir assembly at the other end stage is constructed to separate and discharge the lightest liquid phase. These weir assemblies function to keep the liquid discharge from an inoperative end stages on the same weight phase a would occur from an operating end stage.

US Patent:

50246470, Jun 18, 1991

Filed:

Jun 13, 1989

Appl. No.:

7/365400

Inventors:

Robert T. Jubin - Powell TN
John D. Randolph - Maryville TN

Assignee:

The United States of America as represented by the United States
Department of Energy - Washington DC

International Classification:

B01D 2126
B04B 100

US Classification:

494 37

Abstract:

The invention is directed to a centrifugal contactor for solvent extraction systems. The centrifugal contactor is provided with an annular vertically oriented mixing chamber between the rotor housing and the rotor for mixing process liquids such as the aqueous and organic phases of the solvent extraction process used for nuclear fuel reprocessing. A set of stationary helically disposed vanes carried by the housing is in the lower region of the mixing chamber at a location below the process-liquid inlets for the purpose of urging the liquids in an upward direction toward the inlets and enhancing the mixing of the liquids and mass transfer between the liquids. The upper region of the mixing vessel above the inlets for the process liquids is also provided with a set helically disposed vanes carried by the housing for urging the process liquids in a downward direction when the liquid flow rates through the inlets are relatively high and the liquids contact the vane set in the upper region. The use of these opposing vane sets in the mixing zone maintains the liquid in the mixing zone at suitable levels.