Donn M Matteson

US Patent:

6404836, Jun 11, 2002

Filed:

Feb 12, 1999

Appl. No.:

09/248987

Inventors:

Donn Moore Matteson - South Windsor CT

Assignee:

Westinghouse Electric Company LLC - Pittsburgh PA

International Classification:

G21C 1900

US Classification:

376268, 376269, 376270, 376271, 376272

Abstract:

A removable rail assembly for use with a spent fuel handling machine, including a support rail, a rail guide carried by the support rail, a rail joint connector supported by the rail guide for coupling the rail guide to adjacent rails, and at least one jacking screw supported by the support rail for lifting the support rail assembly. Another embodiment of the invention includes a second jacking screw received in the top surface of the rail guide. The joint connector is tongue and groove joint with a tapered parting line that permits a tight fit between the removable rail and adjacent fixed rails. During removal of the removable rail, the jacking screw distributes a uniform lifting force along the length of the rail, loosening the joint connector. Once the joint connector is loosened, the rail is coupled to a lifting crane and transported to a storage area.

US Patent:

6570950, May 27, 2003

Filed:

Mar 11, 2002

Appl. No.:

10/095632

Inventors:

Donn Moore Matteson - South Windsor CT

Assignee:

Westinghouse Electric Company LLC - Pittsburgh PA

International Classification:

G21C 13024

US Classification:

376461, 376285, 376287, 376293, 376295, 376296, 376918, 52250, 52251, 52252, 52258, 52260, 52300, 52574, 523731, 521731, 52378, 2505061, 2505151, 2505171, 2505181

Abstract:

A nuclear steam supply containment system employing prefabricated component supports that are surrounded by steel concrete forms and anchored to the floor liner of a nuclear containment. The prefabricated component supports extend through the concrete forms and a reinforce concrete slab cap to a support elevation for the component. A second inner steel concrete form can be employed to form an annular concrete channel through which the supports extend. The center of the inner form can be filled with a sand-like substance, radiation absorber material or concrete grout.

US Patent:

20030169839, Sep 11, 2003

Filed:

Mar 11, 2002

Appl. No.:

10/095562

Inventors:

Donn Matteson - South Windsor CT, US

International Classification:

G21C019/00

US Classification:

376/260000

Abstract:

A prefabricated in-core nuclear plant instrumentation chase concrete form is provided that has integral embedment plates at the locations where the in-core instrumentation guide thimble supports contact the walls of the chase. Structural steel shapes are located on the outside of the prefabricated chase at the embedment locations to transfer loads on axially-spaced, transverse, thimble support plates that route and support guide thimbles through which the in-core instrumentation pass, into the surrounding concrete structure. The guide thimble supports are installed in the pre-fabricated chase form at the factory and serve to strengthen the structure during shipping and handling as well as resist the loads applied by the wet concrete poured around the prefabricated chase during installation at a nuclear plant site.

US Patent:

57152888, Feb 3, 1998

Filed:

May 9, 1996

Appl. No.:

8/646402

Inventors:

Donn Moore Matteson - South Windsor CT

Assignee:

Combustion Engineering, Inc. - Windsor CT

International Classification:

G21C 1900

US Classification:

376263

Abstract:

In order to reduce the number of lifts which are required to remove the various equipment normally disposed above the reactor pressure vessel and to make way for refuelling or regular maintenance, the control rod element drive mechanisms are completely enclosed within a cylindrical enclosure which is attached to the head of the pressure vessel. The top of the cylindrical enclosure is closed with a cap-like member which acts as both a missile shield and a head area cable tray. The missile shield, the cylindrical enclosure, the control rod drive mechanisms and the pressure vessel head, are connected to form an integral unit which can be removed in a single lift. Cable trays are pivotally supported on a wall of a building to establish a bridge between the building and the head area cable array and to establish a connection with the control element drive mechanism cables. During lifting, the control element drive mechanism cables are disconnected and the pivotal bridge trays are swung out of the way. During normal operation, the cylindrical enclosure guides a flow of cooling air over the control rod drive mechanisms.

US Patent:

63174774, Nov 13, 2001

Filed:

Apr 7, 1999

Appl. No.:

9/287630

Inventors:

Donn M. Matteson - Windsor CT

Assignee:

Westinghouse Electric Co. LLC - Pittsburgh PA

International Classification:

G21C 13028
F16J 1546

US Classification:

376203

Abstract:

A seal assembly for sealing a space between an annular flange on a nuclear reactor vessel and a surrounding ledge of a refueling canal to provide a temporary water barrier during refueling operations. The seal assembly includes an annular closure plate having an outer portion secured to the surrounding ledge and an inner portion supporting a first sealing surface. A second sealing surface opposing the first sealing surface is formed on or secured to the annular flange of the reactor vessel. An annular space between the first and second sealing surfaces provides a ventilation path from the reactor cavity during normal plant operation. The annular space is sealed by an inflatable seal during refueling operations to provide a water barrier between the refueling canal and the reactor vessel. The inflatable seal is secured to and supported by an annular support structure that straddles the annular space. The annular support structure provides a structure for handling the inflatable seal during installation and removal.

US Patent:

62401548, May 29, 2001

Filed:

Apr 6, 1999

Appl. No.:

9/286660

Inventors:

Donn M. Matteson - South Windsor CT
Daniel A. Peck - South Windsor CT

Assignee:

CE Nuclear Power LLC - Winsdor CT

International Classification:

G21C 900
G21C 712

US Classification:

376298

Abstract:

An augmented cooling system for a CEDM in a nuclear reactor includes self actuated louvers or flap valve louvers which allow hot air from the head lift rig to vent and cooler ambient air to enter the rig in the event that pressure is lost for the forced cooled air which normally cools the CEDM.

US Patent:

55419690, Jul 30, 1996

Filed:

Aug 24, 1994

Appl. No.:

8/295201

Inventors:

Donn M. Matteson - South Windsor CT
Daniel A. Peck - South Windsor CT

Assignee:

Combustion Engineering, Inc. - Windsor CT

International Classification:

G21C 17022

US Classification:

376258

Abstract:

A tank (18) forms a chamber having an upper and lower region. The tank (18) is in even elevation with a horizontal pipe (12) having a top region and a bottom region. An upper connecting pipe (14) fluidly connects the top region of the pipe (12) to the upper region of tank (18). A lower connecting pipe (16) fluidly connects the bottom region of pipe (12) to the lower region of the tank (18). Heat junction thermocouples (22) generate a signal indicative of water in the pipe (12). The signal is transmitted to a remote location by line (24).

US Patent:

43022901, Nov 24, 1981

Filed:

Dec 31, 1979

Appl. No.:

6/108621

Inventors:

Joseph M. Mazur - Ludlow MA
Donn M. Matteson - South Windsor CT

Assignee:

Combustion Engineering, Inc. - Windsor CT

International Classification:

G21C 1920

US Classification:

376287

Abstract:

A head equipment support structure system (HESS) (10) particularly adapted to be cooperatively associated with a nuclear reactor vessel (12) for purposes of effecting a separation of the electrical cables (30) that are utilized in the head area of such a vessel (12), as well as for purposes of providing support for these cables (30). The subject HESS (10) which is in the form of an integral structure that is removably supported relative to the vessel (12) combines the features of cable support structure, missile shield, and cooling ductwork support structure. The HESS (10) embodies horizontally disposed multiple decks (14) to which the cables (30) are vertically routed from the reactor vessel head. The decks (14), which are located in vertically spaced relation directly above the reactor vessel head, support and separate the cables (30). The decks (14) further function to align the corresponding ends of the cables (30) with their respective mating connectors, the latter being associated with the reactor vessel head and the connection panels suitably mounted on the surrounding wall surfaces.