Larry E. Fennern - San Jose CA Charles W. Dillmann - San Jose CA Craig D. Sawyer - San Jose CA Momtaz M. Aburomia - San Jose CA Charles W. Relf - San Jose CA Mark W. Siewert - San Jose CA John C. Walther - San Jose CA
Assignee:
General Electric Company - San Jose CA
International Classification:
G21C 900
US Classification:
376293
Abstract:
A nuclear reactor having a pressure vessel which is open at the top. The open top of the pressure vessel is closed by a steel dome. A containment, which is open at the top, extends upward from and is joined to the top of the pressure vessel and has an open containment head at the top thereof. The open top of the containment is closed by a steel dome, thereby forming a containment well bounded laterally by the containment, on the bottom by the vessel closure and on the top by the containment closure. The pressure vessel can be a steel-lined prestressed concrete vessel, while the containment is formed by an extension of the prestressed concrete vessel. Alternatively, the pressure vessel and the containment are parts of a unitary steel vessel. Isolation valves are installed on each penetration pipeline to isolate the system in the event of a loss-of-coolant accident. An isolation valve located external to the pressure vessel and the portion of the pipeline between that external isolation valve and the interior of the pressure vessel are encased in guard piping.
Removable Shroud And Pump Deck For A Boiling Water Nuclear Reactor
In a pressure vessel of a nuclear reactor containing a core assembly enclosed within a core shroud, the core shroud spaced radially inwardly of a side wall of the pressure vessel with an annular pump deck located in an annular radial space between the core shroud and the side wall of the pressure vessel, the improvement wherein the shroud is removably secured to an annular support leg extending upwardly from the bottom of the pressure vessel; and further wherein the annular pump deck is provided in the form of a plurality of removable segments.
Removable Shroud And Pump Deck For A Boiling Water Nuclear Reactor
In a pressure vessel of a nuclear reactor containing a core assembly enclosed within a core shroud, the core shroud spaced radially inwardly of a side wall of the pressure vessel with an annular pump deck located in an annular radial space between the core shroud and the side wall of the pressure vessel, the improvement wherein the shroud is removably secured to an annular support leg extending upwardly from the bottom of the pressure vessel; and further wherein the annular pump deck is provided in the form of a plurality of removable segments.
Charles A. Dalke - San Jose CA Charles W. Dillmann - Morgan Hill CA Charles W. Relf - Fremont CA
Assignee:
General Electric Company - Schenectady NY
International Classification:
G21C 332
US Classification:
376434
Abstract:
A fuel bundle assembly for a boiling water nuclear reactor includes an open ended tubular channel subdivided into four quadrants by at least two interior partitions, each quadrant having a sub-fuel bundle assembly having a plurality of fuel rods extending between upper and lower tie plates. An inter-bundle support plate receives a lower end of the channel and has four flow openings at an upper end thereof, such that the lower tie plate of each sub-fuel bundle supported in a respective one of the openings in the support plate. In one embodiment, the sub-fuel bundles within a channel are separated by a cruciform shaped coolant passage. In a second embodiment, the cruciform coolant passage is omitted to thus provide a homogeneous sub-fuel bundle configuration.
Removable Retrofit Shroud For A Boiling Water Nuclear Reactor And Associated Method
In a pressure vessel of a nuclear reactor containing a core assembly enclosed within a core shroud, the shroud spaced radially inwardly of a side wall of the pressure vessel, and an annular pump deck welded in a place in an annular radial space between the core shroud and the side wall of the pressure vessel. The shroud provided with a radially outwardly extending flange seated on and removably secured to the pump deck. Wedge elements are interposed between flange portions and the side wall.
Irvin R. Kobsa - San Jose CA Charles W. Relf - Sunnyvale CA John C. Carruth - San Jose CA
Assignee:
General Electric Company - San Jose CA
International Classification:
G21C 716
US Classification:
376230
Abstract:
A hydraulically based control rod drive system that is contained within the pressure vessel is disclosed for positioning the control rods relative to fuel rods positioned in a nuclear core of a boiling water reactor. Hydraulic jacks mounted on an open grid located entirely within the pressure vessel at a position above the nuclear core are used to position the control rods. Suitable jack and grid structures, as well as a hydraulic control arrangements are described.