Patent Number: 
Section: claims

1. A method of servicing a nuclear reactor during a reactor outage, the reactor comprising a primary containment vessel and a reactor pressure vessel positioned in the primary containment vessel, said method comprising:positioning a servicing platform above the reactor pressure vessel, the servicing platform comprising:a frame comprising a plurality of interconnected beams;a support structure attached to the frame;a floor attached to a top of the frame, the floor comprising a reactor access opening sized to permit access to the reactor pressure vessel; andat least one auxiliary platform movably coupled to the frame and extending into the access opening, the at least one auxiliary platform movable along a perimeter of the access opening of the floor; andperforming predetermined servicing operations on the reactor. 2. A method in accordance with claim 1 wherein the servicing platform access opening has a circular, elliptical, or polygonal shape. 3. A method in accordance with claim 1 wherein the servicing platform comprises at least one of steel, aluminum, and a thermoplastic and fiber composite material. 4. A method in accordance with claim 1 wherein the reactor comprises at least two refuel bridges spaced apart and located in the primary containment above the reactor pressure vessel, and positioning a servicing platform above the reactor pressure vessel comprises positioning the servicing platform with the servicing platform support structure engaging the refuel bridges to suspend the servicing platform from the two spaced apart refuel bridges. 5. A method in accordance with claim 1 wherein the primary containment comprises a refuel floor located above the pressure vessel, the refuel floor comprising a plurality of crane rails, the support structure comprising a plurality of wheels, and positioning a servicing platform above the reactor pressure vessel comprises positioning the servicing platform with the servicing platform support structure wheels engaging the crane rails. 6. A method in accordance with claim 1 wherein the primary containment comprises a refueling floor located above the pressure vessel, and positioning a servicing platform above the reactor pressure vessel comprises positioning the servicing platform with the servicing platform support structure engaging the refueling floor to support the servicing platform above the pressure vessel. 7. A method in accordance with claim 6 wherein the refuel floor comprises a pressure vessel access opening and a ledge extending circumferentially around the pressure vessel access opening, and positioning a servicing platform above the reactor pressure vessel comprises positioning the servicing platform with the servicing platform support structure engaging the ledge to support the servicing platform above the pressure vessel. 8. A method in accordance with claim 1 wherein the servicing platform further comprises at least one lifting device movably coupled to the frame, the at least one lifting device movable along a perimeter of the access opening. 9. A method in accordance with claim 1 wherein positioning a servicing platform above the reactor pressure vessel comprises:assembling the reactor servicing platform inside the primary containment vessel; andmoving the reactor servicing platform into position above the reactor pressure vessel. 10. A method in accordance with claim 9 wherein assembling the reactor servicing platform inside the primary containment vessel comprises coupling modular sections of the reactor servicing platform together, each modular section comprising at least one of a portion of the frame, a portion of the support structure, and a portion of the floor.