Richard Albert Karnesky

US Patent:

45681112, Feb 4, 1986

Filed:

Aug 29, 1983

Appl. No.:

6/527547

Inventors:

David W. Christiansen - Kennewick WA
Richard A. Karnesky - Richland WA

Assignee:

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

International Classification:

F16L 3712
G21C 306

US Classification:

285 92

Abstract:

A locking connection for releasably attaching a handling socket to the duct tube of a fuel assembly for a nuclear reactor. The connection comprises a load pad housing mechanically attached to the duct tube and a handling socket threadably secured within the housing. A retaining ring is interposed between the housing and the handling socket and is formed with a projection and depression engageable within a cavity and groove of the housing and handling socket, respectively, to form a detachable interlocked connection assembly.

US Patent:

47103434, Dec 1, 1987

Filed:

Nov 27, 1985

Appl. No.:

6/802559

Inventors:

David W. Christiansen - Kennewick WA
Richard A. Karnesky - Richland WA

Assignee:

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

International Classification:

G21C 320

US Classification:

376414

Abstract:

An improved cesium getter 28 is provided in a breeder reactor fuel element or pin in the form of an extended surface area, low density element formed in one embodiment as a helically wound foil 30 located with silicon carbide, and located at the upper end of the fertile material upper blanket 20.

US Patent:

H6890, Oct 3, 1989

Filed:

Nov 24, 1987

Appl. No.:

7/124709

Inventors:

David W. Christiansen - Kennewick WA
Richard A. Karnesky - Richland WA
Robert D. Leggett - Richland WA
Ronald B. Baker - Richland WA

Assignee:

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

International Classification:

G21C 300

US Classification:

376361

Abstract:

A fuel pin for a liquid metal nuclear reactor is provided. The fuel pin includes a generally cylindrical cladding member with metallic fuel material disposed therein. At least a portion of the fuel material extends radially outwardly to the inner diameter of the cladding member to promote efficient transfer of heat to the reactor coolant system. The fuel material defines at least one void space therein to facilitate swelling of the fuel material during fission.

US Patent:

46541942, Mar 31, 1987

Filed:

Sep 9, 1985

Appl. No.:

6/773891

Inventors:

David W. Christiansen - Kennewick WA
Richard A. Karnesky - Richland WA
Donald R. Precechtel - Richland WA
Bob G. Smith - Richland WA
Ronald C. Knight - Richland WA

Assignee:

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

International Classification:

G21C 332

US Classification:

376443

Abstract:

An inlet nozzle assembly for directing coolant into the duct tube of a fuel assembly attached thereto. The nozzle assembly includes a shell for housing separable components including an orifice plate assembly, a neutron shield block, a neutron shield plug, and a diffuser block. The orifice plate assembly includes a plurality of stacked plates of differently configurated and sized openings for directing coolant therethrough in a predesigned flow pattern.

US Patent:

48184799, Apr 4, 1989

Filed:

Oct 4, 1985

Appl. No.:

6/784277

Inventors:

David W. Christiansen - Kennewick WA
Richard A. Karnesky - Richland WA

Assignee:

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

International Classification:

G21C 334

US Classification:

376442

Abstract:

The invention relates to a nuclear reactor spacer grid member for use in a liquid cooled nuclear reactor and to a ductless core component employing a plurality of these spacer grid members. The spacer grid member is of the egg-shell type and is constructed so that the walls of the cell members of the grid member are formed of a single thickness of metal to avoid tolerance problems. Within each cell member is a hydraulic spring which laterally constrains the nuclear material bearing rod which passes through each cell member against a hardstop in response to coolant flow through the cell member. This hydraulic spring is also suitable for use in a water cooled nuclear reactor. A core component constructed of, among other components, a plurality of these spacer grid members, avoids the use of a full length duct by providing spacer sleeves about the sodium tubes passing through the spacer grid members at locations between the grid members, thereby maintaining a predetermined space between adjacent grid members.