DAVID A ALTMAN
Engineers in Pittsburgh, PA

License number
Pennsylvania PE027053E
Category
Engineers
Type
Professional Engineer
Address
Address
Pittsburgh, PA 15239

Professional information

David Altman Photo 1

Remotely Replaceable Fuel Assembly Alignment Pin

US Patent:
5297176, Mar 22, 1994
Filed:
May 22, 1992
Appl. No.:
7/887264
Inventors:
David A. Altman - Plum PA
James R. Chrise - Trafford PA
Bruce W. Bevilacqua - Export PA
Gregory L. Calhoun - Allegheny Township, Westmoreland County PA
Assignee:
Westinghouse Electric Corp. - Pittsburgh PA
International Classification:
G21C 506
US Classification:
376364
Abstract:
The guide pin aligning a top nozzle of a nuclear fuel assembly to an upper core plate of a nuclear reactor, is replaced working exclusively from below the upper core plate. The replacement guide pin has a shaft portion engaged with the upper core plate and the clamping nut which held the original guide pin, by threadable connection and/or by an expansion fitting. A shoulder on the pin bears against a lower surface of the upper core plate, and a nose of the pin is received in the top nozzle of the fuel assembly. A preferred expansion fitting has a bushing with ridges on its outer surface and a conical inside surface, and is inserted into the bored out original guide pin shaft. A threaded conical plug is pulled axially with rotation of the replacement pin shaft to expand the bushing. The ridges rigidly lock the replacement pin between the shoulder and the clamping nut. By attaching the replacement pin to the stub of the original pin, the invention utilizes existing attachments of the original pin to the upper core plate.


David Altman Photo 2

Nuclear Reactor Alignment Plate Configuration

US Patent:
8638900, Jan 28, 2014
Filed:
Sep 14, 2007
Appl. No.:
11/855196
Inventors:
David A. Altman - Pittsburgh PA, US
David R. Forsyth - Cheswick PA, US
Richard E. Smith - Harrison City PA, US
Norman R. Singleton - Murrysville PA, US
Assignee:
Westinghouse Electric Company LLC - Cranberry Township PA
International Classification:
G21C 1/04
US Classification:
376353, 376347, 376461
Abstract:
An alignment plate that is attached to a core barrel of a pressurized water reactor and fits within slots within a top plate of a lower core shroud and upper core plate to maintain lateral alignment of the reactor internals. The alignment plate is connected to the core barrel through two vertically-spaced dowel pins that extend from the outside surface of the core barrel through a reinforcement pad and into corresponding holes in the alignment plate. Additionally, threaded fasteners are inserted around the perimeter of the reinforcement pad and into the alignment plate to further secure the alignment plate to the core barrel. A fillet weld also is deposited around the perimeter of the reinforcement pad. To accommodate thermal growth between the alignment plate and the core barrel, a gap is left above, below and at both sides of one of the dowel pins in the alignment plate holes through which the dowel pins pass.


David Altman Photo 3

Upper Internals Arrangement For A Pressurized Water Reactor

US Patent:
8483347, Jul 9, 2013
Filed:
Apr 10, 2007
Appl. No.:
11/733248
Inventors:
Norman R. Singleton - Murrysville PA, US
David A. Altman - Pittsburgh PA, US
Ching Yu - Murrysville PA, US
James A. Rex - Trafford PA, US
David R. Forsyth - Cheswick PA, US
Assignee:
Westinghouse Electric Company LLC - Cranberry Township PA
International Classification:
G21C 1/04
US Classification:
376353, 376245, 376254, 376255
Abstract:
In a pressurized water reactor with all of the in-core instrumentation gaining access to the core through the reactor head, each fuel assembly in which the instrumentation is introduced is aligned with an upper internals instrumentation guide-way. In the elevations above the upper internals upper support assembly, the instrumentation is protected and aligned by upper mounted instrumentation columns that are part of the instrumentation guide-way and extend from the upper support assembly towards the reactor head in hue with a corresponding head penetration. The upper mounted instrumentation columns are supported laterally at one end by an upper guide tube and at the other end by the upper support plate.


David Altman Photo 4

Nuclear Reactor Downcomer Flow Deflector

US Patent:
7889830, Feb 15, 2011
Filed:
May 8, 2007
Appl. No.:
11/745600
Inventors:
Charles B. Gilmore - Greensburg PA, US
David A. Altman - Pittsburgh PA, US
Norman R. Singleton - Murrysville PA, US
Assignee:
Westinghouse Electric Company LLC - Cranberry Township PA
International Classification:
G21C 3/34, G21C 9/00
US Classification:
376439, 376282, 376294
Abstract:
A nuclear reactor having a coolant flow deflector secured to a reactor core barrel in line with a coolant inlet nozzle. The flow deflector redirects incoming coolant down an annulus between the core barrel and the reactor vessel. The deflector has a main body with a front side facing the fluid inlet nozzle and a rear side facing the core barrel. The rear side of the main body has at least one protrusion secured to the core barrel so that a gap exists between the rear side of the main body adjacent the protrusion and the core barrel. Preferably, the protrusion is a relief that circumscribes the rear side of the main body.


David Altman Photo 5

Reactor Pressure Vessel

US Patent:
7120219, Oct 10, 2006
Filed:
Nov 5, 2004
Appl. No.:
10/982068
Inventors:
David R. Forsyth - Cheswick PA, US
David A. Altman - Pittsburgh PA, US
Kevin G. Bethune - Pittsburgh PA, US
Michael F. Hankinson - Monroeville PA, US
Robert H. McFetridge - Level Green PA, US
Assignee:
Westinghouse Electric CO, LLC - Pittsburgh PA
International Classification:
G21C 9/00
US Classification:
376294, 376205, 376263
Abstract:
A reactor pressure vessel supports the flanges of a core barrel assembly and an upper support plate. These flanges have aligned holes for diverting inlet coolant water to the vessel head for cooling the head. The aligned holes have different cross-sectional areas for controlling unexpected backflow of coolant water from the vessel head around the periphery of the upper support plate.


David Altman Photo 6

Reactor Pressure Vessel

US Patent:
6888909, May 3, 2005
Filed:
Mar 27, 2003
Appl. No.:
10/401284
Inventors:
David R. Forsyth - Cheswick PA, US
David A. Altman - Pittsburgh PA, US
Kevin G. Bethune - Pittsburgh PA, US
Michael F. Hankinson - Monroeville PA, US
Robert H. McFetridge - Level Green PA, US
Assignee:
Westinghouse Electric Company LLC - Pittsburgh PA
International Classification:
G21C009/00
US Classification:
376294, 376205
Abstract:
A reactor pressure vessel supports the flanges of a core barrel assembly and an upper support plate. These flanges have aligned holes for diverting inlet coolant water to the vessel head for cooling the head. The aligned holes have different cross-sectional areas for controlling unexpected backflow of coolant water from the vessel head around the periphery of the upper support plate.