摘要:
A handling system including a tool for lifting the container, wherein the lifting tool includes a lifting carrier to be suspended and a member for gripping the container comprising removable devices for fastening the container onto the gripping member.According to one aspect of the invention, the gripping member is mounted so that it may rotate on the lifting carrier about a substantially horizontal rotation axis when the lifting carrier is suspended.
摘要:
The installation provided includes at least one structure for receiving and holding guide tubes and structural elements; a carriage movable parallel to the guide tubes; at least one welding tool; and displacement means for moving the welding tool, the displacement means connecting the pincer to the carriage and presenting at least six degrees of freedom.
摘要:
The invention relates to a method for regulation of operational parameters of the core of a pressurised water nuclear reactor comprising: a step of acquisition of values (FH, FB, TBC, TBF, Q) which are representative of the conditions of operating of the core of the reactor; a step of evaluation of the actual values (Tmoye, AOe, {circumflex over (P)} maxe) of the operational parameters at least according to the values acquired (FH, FB, TBC, TBF, Q); a step of selection of a control law for the concentration of a neutron-absorbent component ([B]) and for the positions of insertion (Z1 to Z5) of the groups (P1 to P5) of rods selected from at least the first and second control laws which are different from one another; and a step of regulation of the operational parameters by means of the control law selected, according to set points (Tmoyc, AOc, {circumflex over (P)} maxc) relative to the said parameters and to the actual values (Tmoye, AOe, {circumflex over (P)} maxe) evaluated.
摘要:
A joint tong apparatus for a radiation shielding facility. A spherical ball has a through-hole. An inner spherical socket and an outer spherical socket are installed in a hole formed in a partition between a radiation-shielded room and a control room so as to enclose the spherical ball on inner and outer sides. A bar is inserted and coupled into and to the through-hole of the spherical ball. An inner joint assembly has a first housing coupled to a shielded room-side end of the bar and a first pivot member pivotably mounted on a free end of the first housing. An outer joint assembly having a second housing coupled to a control room-side end of the bar and a second pivot member pivotably mounted on a free end of the second housing. The apparatus further includes a tong assembly, a handle assembly, a tong manipulation cable, and a pair of pivot manipulation cables.
摘要:
A fuel rack for supporting radioactive fuel assemblies in an underwater (or other submerged) environment that reduces the depth required for the pool to effectuate the fuel rack loading procedure. The fuel rack is specially designed to afford lateral loading. In one embodiment, the fuel rack comprises a body structure comprising at least one substantially vertically oriented elongated cell for receiving a nuclear fuel assembly, the body having a top, a bottom and a first lateral side; at least one elongated slot in the first lateral side of the body structure that forms a passageway into the cell through which a vertically oriented fuel assembly can be loaded; and means for supporting a fuel assembly within the cell in a substantially vertical orientation. In another embodiment, the invention is a method of laterally loading a fuel rack that utilizes rotation of the fuel assembly to secure the fuel assembly within its designated cell.
摘要:
A method for delivery of a tool into a submerged bore includes controlling the movement of a tool delivery device in the pool by operating at least one propulsion drive located on the tool delivery device. The tool delivery device is coupled to an inlet to the bore and a tool is inserted from the tool delivery device through the inlet and into the bore.
摘要:
A method of determining a threshold value of a nuclear reactor operating parameter having the steps of simulating at least a transient operational occurrence of the nuclear reactor, calculating the value reached by a physical quantity during the transient operational occurrence in at least a cladding of a fuel rod of the reactor and establishing, as a limit value of an operational parameter of the reactor, the value of the operational parameter when the value calculated the step of calculating the value reached by a physical quantity during the transient operational occurrence which corresponds to a value of the physical quantity which characterizes a failure of the cladding.
摘要:
A protective screen includes a front wall (1), connected to a lateral wall (2) running perpendicular or essentially perpendicular to the front wall (1), the walls (1, 2) including transparent panels (8, 10) over at least a part of the height thereof. The upper part (8) of the front wall (1) is inclined forwards, forming an overhang which permits the operator to approach the working region and with two holes (11, 12) to permit the passage of the operator's arms.
摘要:
An In Orbit Transportation & Recovery System (IOSTAR™) (10) is disclosed. One preferred embodiment of the present invention comprises a space tug powered by a nuclear reactor (19). The IOSTAR™ includes a collapsible boom (11) connected at one end to a propellant tank (13) which stores fuel for an electric propulsion system (12). This end of the boom (11) is equipped with docking hardware (14) that is able to grasp and hold a satellite (15) and as a means to refill the tank (13). Radiator panels (16) mounted on the boom (11) dissipate heat from the reactor (19). A radiation shield (20) is situated next to the reactor (19) to protect the satellite payload (15) at the far end of the boom (11). The IOSTAR™ (10) will be capable of accomplishing rendezvous and docking maneuvers which will enable it to move spacecraft between a low Earth parking orbit and positions in higher orbits or to other locations in our Solar System.
摘要:
A reactor servicing platform for a nuclear reactor is provided. The nuclear reactor includes a reactor pressure vessel positioned in a primary containment and at least one refuel bridge. The primary containment includes a refueling floor. The servicing platform, in an exemplary embodiment, includes a frame, a support structure, and a floor covering the frame. The floor includes a reactor access opening sized to permit access to the reactor pressure vessel.