Combustion Engineering, Inc.

Other

Edward A Siegel

David J Ayres

Glen E Schukei

Frank J Formanek

Kenneth V Margotta

Francis X McDonald

Richard C Noyes

Christo Andrea

Clive Frederick Dupen

Robert H Brookins

Scott A Kendrick

George J Roebelen

Donald Martin Barrus

Pete Leombruni

Michael S McDonald

An irradiated steel pressurized nuclear reactor pressure vessel 10 is provided with a crack initiation retarding and crack extension retarding reactor vessel integrity girdle 20 or 120 made up of shoes or links 22, with mechanical take up joints (26 to 34a or 126 to 134a). Instead of pivoted shoe links 22, the girdle 120 may be made using constricting roller chain links 122. In any event, crack initiation and crack extension which may result from pressure loading or vessel material embrittled in the beltline region by neutron bombardment is retarded by maintenance of a prestress under the nozzles during all periods of operation of the reactor.

Method of retarding irradiated nuclear vessel crack initiation and

A data acquisition system (1) by which environmental parameters proximate to plant installed valves (2) may be monitored, recorded and correlated with other valve operating data. The system includes sensors (8) for sensing environmental parameters such as gas/vapor concentration, temperature or humidity. The system also includes sensors for sensing changes in the actuating variable (34) and sensors for sensing valve stem displacement (58). The sensors (8, 34, 6) generate electrical signals proportional to the value of the sensed parameter. First data interface equipment (32, 42, 43) is provided for digitizing the sensed actuating variable as the actuating variable is changed to displace the stem, preferably a full stroke from the open-to-close-to-open positions or vice versa. Second data interface equipment (7, 45) is provided for digitizing the sensed environmental parameter as the stem is displaced. Third data interface equipment (6, 45) is provided for digitizing the sensed stem displacement. The digitized data are stored, preferably with a computer (45) and associated random access memory, and can later be uploaded for use in, for example, a plant database system or correlated to evaluate valve operability.

Valve diagnostic environmental data acquisitioner

A permanent pool seal and neutron shield 30 for providing an effective water barrier over the annular space 28 between a nuclear reactor vessel flange 24 and a surrounding annular ledge 22 includes annular deck sections 32 supported on spaced ribs 46. Flexible membranes 50,52 on the deck section peripheries accommodate relative movement. Openings 42, each with a removable plug structure which includes cover 44 and tapered can 60, provide vessel cavity 14 with ventilation and maintenance access. All cans 60 and similar containers 56 and 59 under the deck structure and flange 24 contain a shielding material 58 in the form of a boron-containing concrete. Supported below the cans is refractory insulating material 54.

Permanent refueling pool seal

The present invention relates to a windmill power system, particularly a passive solar powered windmill. Specifically, the present invention is directed to a windmill in which a solar chamber and a stack produce an upwardly flowing natural convection draft which is utilized to turn the blades of a horizontally positioned windmill. A conventional vertical windmill may also be used in conjunction with the horizontal windmill. The invention can also be used in a cogeneration system or with any heat source, with waste heat being used to heat the air in the solar chamber.

Windmill power system

An improved core servicing apparatus for a nuclear reactor having a vessel, a head for the vessel, one or more penetration openings in the head and a core within the vessel of the type having an array of fuel assemblies and including apertures in the array for neutron absorbers. The servicing apparatus includes a support column adapted to be supported by and depend from the head in registry with a penetration opening; a plurality of core servicing elements which may include neutron absorber actuating means and/or instrument packages are supported by the support column; and means are provided for laterally displacing at least some of the servicing elements relative to the support column between a laterally compact and a laterally expanded configuration. In one embodiment, instruments may be located at the lower end of long resilient cables and are longitudinally movable within and beyond guide channels supported by the support column. The guide channels are directed outward at their lower ends to direct a descending instrument and cable outwardly.

Control rod and/or instrument tree assembly

A device is provided which is installed in a reactor prior to carrying out refueling operations and which accurately locates and isolates a selected core location to permit rapid withdrawal and insertion of fuel subassemblies at that location. A shielded plug designed to cooperate with the refueling apparatus is inserted into an access port in the reactor head. A structural shroud extends down from the plug and carries at its lower end a radially floating, hexagonal spreader tube with mechanisms to rotate it for angular alignment purposes and a linear drive for inserting it into the core. The upper end of the spreader tube serves as a guide for leading the fuel handling apparatus into alignment with the chosen subassembly.

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West Hartford, CT, United States of America

Edward A Siegel