Patent classifications
G21C7/12
Flux-shifting reactivity control system
A control assembly for a nuclear reactor includes a first reactivity control assembly having a first neutron modifying material, a second reactivity control assembly having a second neutron modifying material, and at least one drive mechanism coupled to the first neutron modifying material and the second neutron modifying material. The first neutron modifying material and the second neutron modifying material are selectively repositionable relative to a fuel region of the nuclear reactor. The at least one drive mechanism is configured to provide the first neutron modifying material and the second neutron modifying material in different directions through the fuel region thereby shifting a flux distribution within the fuel region away from the second neutron modifying material.
AN ASSEMBLY FOR CONTROLLING DISENGAGEMENT BETWEEN A CONTROL CLUSTER AND A DRIVE ROD OF A DEVICE FOR CONTROLLING THE REACTIVITY OF A NUCLEAR REACTOR
A control assembly (10) for a nuclear reactor includes a reactivity control device (11) comprising a control rod cluster (12) comprising an attaching head (22), and a drive rod (14) comprising an attaching device (16) for attaching the drive rod (14) to the attaching head (22). The attaching device (16) is movable between a connection position and a disconnection position. The drive rod (14) and the attaching device (16) define an axial trough recess (34) forming a sleeve (35). A checking device (13) engages with the reactivity control device (11) comprising a probe rod (36) which is free to move translationally in the sleeve (35) and comprises a lower end (38) abutting the attaching head (22) of the control rod cluster (12).
AN ASSEMBLY FOR CONTROLLING DISENGAGEMENT BETWEEN A CONTROL CLUSTER AND A DRIVE ROD OF A DEVICE FOR CONTROLLING THE REACTIVITY OF A NUCLEAR REACTOR
A control assembly (10) for a nuclear reactor includes a reactivity control device (11) comprising a control rod cluster (12) comprising an attaching head (22), and a drive rod (14) comprising an attaching device (16) for attaching the drive rod (14) to the attaching head (22). The attaching device (16) is movable between a connection position and a disconnection position. The drive rod (14) and the attaching device (16) define an axial trough recess (34) forming a sleeve (35). A checking device (13) engages with the reactivity control device (11) comprising a probe rod (36) which is free to move translationally in the sleeve (35) and comprises a lower end (38) abutting the attaching head (22) of the control rod cluster (12).
STATIONARY ISOLATED ROD COUPLINGS FOR USE IN A NUCLEAR REACTOR CONTROL ROD DRIVE
Control rod drives include linearly-moveable control elements inside an isolation barrier. Control rod drives move the control element through secured magnetic elements subject to magnetic fields. Induction coils may generate the magnetic fields across a full stroke length of the control element in the reactor. A closed coolant loop may cool the induction coils, which may be in a vacuum outside the isolation barrier. A control rod assembly may house the magnetic elements and directly, removably join to the control element. The control rod assembly may lock with magnetic overtravel latches inside the isolation barrier to maintain an overtravel position. Overtravel release coils outside the isolation barrier may release the latches to leave the overtravel position. Methods of operation include selectively energizing or de-energizing induction coils to drive the control element to desired insertion points, including full insertion by gravity following de-energization. No direct connection may penetrate the isolation barrier.
STATIONARY ISOLATED ROD COUPLINGS FOR USE IN A NUCLEAR REACTOR CONTROL ROD DRIVE
Control rod drives include linearly-moveable control elements inside an isolation barrier. Control rod drives move the control element through secured magnetic elements subject to magnetic fields. Induction coils may generate the magnetic fields across a full stroke length of the control element in the reactor. A closed coolant loop may cool the induction coils, which may be in a vacuum outside the isolation barrier. A control rod assembly may house the magnetic elements and directly, removably join to the control element. The control rod assembly may lock with magnetic overtravel latches inside the isolation barrier to maintain an overtravel position. Overtravel release coils outside the isolation barrier may release the latches to leave the overtravel position. Methods of operation include selectively energizing or de-energizing induction coils to drive the control element to desired insertion points, including full insertion by gravity following de-energization. No direct connection may penetrate the isolation barrier.
INTEGRATED IN-VESSEL NEUTRON SHIELD
To reduce size and mass of a nuclear reactor system, an integrated in-vessel shield separates the role of a neutron reflector and a neutron shield. Nuclear reactor system includes a pressure vessel including an interior wall and a nuclear reactor core located within the interior wall of the pressure vessel. Nuclear reactor core includes a plurality of fuel elements and at least one moderator element. Nuclear reactor system includes a reflector located inside the pressure vessel that includes a plurality of reflector blocks laterally surrounding the plurality of fuel elements and the at least one moderator element. Nuclear reactor system includes the in-vessel shield located on the interior wall of the pressure vessel to surround the reflector blocks. In-vessel shield is formed of two or more neutron absorbing materials. The two more neutron absorbing materials include a near black neutron absorbing material and a gray neutron absorbing material.
REPLACEMENT THERMAL SLEEVE FOR A REACTOR VESSEL CLOSURE HEAD PENETRATION ADAPTER OF CONTROL ROD DRIVE MECHANISM
A replacement thermal sleeve with a flange for a reactor vessel closure head penetration adapter housing. By altering a diameter of the flange, a replacement thermal sleeve can be installed through the narrow diameter of the penetration adapter housing opening from under the reactor vessel head. The flange can be compressible or expandable or the tubular wall of the thermal sleeve can be inserted in longitudinal sections, one at a time, into an opening in the underside of the penetration head adapter and reformed within the opening when fully inserted.
NUCLEAR REACTOR
A nuclear reactor includes a reactor container, a reactor core, a control drum assembly, a hot channel, a heat exchanger and a main pump. The reactor container contains a coolant; the reactor core is arranged at a lower middle part of the reactor container; the control drum assembly is arranged on an outer periphery of the reactor core, and includes control drums arranged at intervals along a peripheral direction of the reactor core; the hot channel is arranged in the reactor container and located above the reactor core. The hot channel has a bottom hermetically connected to the control drum assembly and a top hermetically connected to an inner top surface of the reactor container. The hot channel has a hot pool passage for the coolant to pass through. The heat exchanger is arranged in the reactor container and located on an outer periphery of the hot channel.
METHOD AND DEVICE FOR REPLACING CONTROL ROD DRIVES
A control rod drive replacement device is provided. The control rod drive replacement device includes a first channel for mounting on a support under a nuclear reactor pressure vessel; a first control rod drive extractor removably received in the first channel, the first control rod drive extractor including a first housing configured for receiving a first control rod drive, the first housing being movable between a horizontal orientation in which the first housing is aligned within the first channel and a vertical orientation in which the first housing is aligned for receiving the first control rod drive from the nuclear reactor pressure vessel; a second channel connected on top of the first channel under the nuclear reactor pressure vessel; and a second control rod drive extractor removably received in the second channel, the second control rod drive extractor including a second housing configured for receiving a second control rod drive, the second housing being movable between a horizontal orientation in which the second housing is aligned within the second channel and a vertical orientation in which the second housing is aligned for receiving the second control rod drive from the nuclear reactor pressure vessel.
METHOD AND DEVICE FOR REPLACING CONTROL ROD DRIVES
A control rod drive replacement device is provided. The control rod drive replacement device includes a first channel for mounting on a support under a nuclear reactor pressure vessel; a first control rod drive extractor removably received in the first channel, the first control rod drive extractor including a first housing configured for receiving a first control rod drive, the first housing being movable between a horizontal orientation in which the first housing is aligned within the first channel and a vertical orientation in which the first housing is aligned for receiving the first control rod drive from the nuclear reactor pressure vessel; a second channel connected on top of the first channel under the nuclear reactor pressure vessel; and a second control rod drive extractor removably received in the second channel, the second control rod drive extractor including a second housing configured for receiving a second control rod drive, the second housing being movable between a horizontal orientation in which the second housing is aligned within the second channel and a vertical orientation in which the second housing is aligned for receiving the second control rod drive from the nuclear reactor pressure vessel.