摘要:
A nuclear reactor includes a pressure vessel enclosing a plenum, a core in the pressure vessel, a pressure-tight encapsulation in the pressure vessel communicating with the plenum, and control members passing through the encapsulation and having first and second control member segments. The second control member segment has an absorber part to be at least partly inserted into and retracted out of the core for controlling reactivity. The first control member segment has an outer drive part. A control drive is associated with the outer drive part for adjusting the control member along the longitudinal direction thereof. An antieject device for restraining ejection of the control member out of the pressure vessel due to a leak at the encapsulation includes a rod coupling having a disengageable coupling catch interconnecting the first and second control member segments and remaining in engagement during normal control motion of the control member and means for unlocking the coupling catch. After disconnection the second control member segment and the absorber part remain in the core for assuming a position fully inserted into the core.
摘要:
An austenitic steel excellent in resistance to neutron irradiation embrittlement which contains, by weight, not more than 0.03% carbon, not more than 1% silicon, 5 to 25% manganese, 15 to 26% chromium, and 10 to 20% nickel, the ratio of atomic volume of chromium to the average atomic volume of matrix of the steel being from 0.900 to 1.030. It is possible to add to the austenitic steel, besides the above-mentioned alloying elements, at least one element selected from the group consisting of niobium, titanium, zirconium, tantalum and vanadium which are effective in corrosion resistance and irradiation embrittlement under neutron irradiation in total amounts of not more than 1.0%. At least one of components composing the inside of a nuclear reactor or nuclear fusion reactor is made of the austenitic steel.
摘要:
In a boiling water nuclear reactor having its core, fuel support casting, and control rod guide tubes removed to expose the core plate, a method for the submerged welding repair and replacement of the control rod drive housing at the bottom extremity of the reactor vessel is disclosed. An alignment device registers to a hole in the core plate and its corresponding guide pin. A control rod drive housing mating fixture on the depending extremity of the shaft of the alignment device precisely fits and mates to the top of the control rod drive housing. The alignment device includes cross electronic levels sealed for submersion which levels remotely transfer through attached wiring the precise angularity between the top of the control rod drive housing on one hand and the corresponding and overlying hole in the core plate on the other hand. For the welding repair process herein, a welding cylinder apparatus fits over the depending end of the shaft of the alignment device. This welding cylinder protrudes downwardly and around the control rod drive housing mating to the stub tube through which the control rod drive housing is inserted. In the embodiment here illustrated, a rotating raceway is provided interior of the chamber for permitting TIG welding unit to traverse around a path for weldment defined at the side of the control rod drive housing and at the top of the stub tube.
摘要:
Control clusters, each of which comprises a plurality of neutron-absorbing rods, are operable by means of electromagnetic mechanisms whose coils are powered by power bridges driven from a control desk (11). The control system includes a controlling hard-wired logic circuit (12) serving the desk and supervising a plurality of hard-wired logic interfaces each of which serves a subgroup (10) of electromagnetic mechanisms for a determined number of clusters. The static power assemblies (9) each including a hard-wired logic interface and the power bridges of the subgroup(s) (10) served thereby are successively and independently replaced by at least one electronic power assembly (23) constituted by a computer and the power bridges of a subgroup served thereby.
摘要:
A support pin system (10) for fastening nuclear reactor guide tube flanges (14) to a nuclear reactor upper core plate (12) includes a support pin (16) having a lower portion (20) frictionally disposed within the upper core plate (12), while an upper section (24) is disposed within a through-bore (22) of the guide tube flange (14). The support pin (16) includes a threaded region (30) upon which is threadedly mounted a nut (32). In order to prevent retrograde rotation of the nut (32) relative to the support pin (16), a locking cap (46) is mounted upon the nut (32) and support pin (16) such that first crimped sections (48) are engaged within apertures (44) defined within the nut (32), while second crimped sections (54) are engaged within longitudinal grooves (50) defined upon the external surface of the support pin (16).
摘要:
Device and method for retaining a linearly movable element in a nuclear reactor. The device comprises, for each shaft, a base fixed to the top part of the reactor internals and coaxial with a shaft guide tube; several grippers or catches spaced apart about the axis of the base and mounted for pivotal movement about a horizontal axis towards a position into and out of engagement with a portion, having circumferential grooves, of the shaft contained in the tube; a slide movable axially on the base towards a top position where it causes engagement of the catches in a groove of the rod, and out of such position; and springs bearing on the base and tending to engage the catches on the shaft. The slide is dimensioned so as to be held by the corresponding sleeve projecting through the reactor vessel cover in a position sufficiently distant from the low position for the catches to be released, whatever the temperature in the reactor.
摘要:
The electromagnetic device is suitable for use in actuating a pressurized water reactor control bar. It comprises a shaft and a fluid-tight casing in which are movable longitudinally a first and a second sets of grippers for gripping the shaft, staggered in the longitudinal direction. The first set of grippers is associated with a movable pole co-operating with a holding coil, carried by the casing and movable by energization and de-energization of the coil between a position in which the first set of grippers holds the shaft and a position in which it releases it. The second set of grippers is associated with a movable plunger co-operating with a transfer coil and movable by energization and de-energization of the transfer coil to and from a position in abutment against an other pole. The other pole is movable between two positions spaced apart by a given step. The movable pole belongs to a mechanism for cutting off a path coolant fluid constituting a thermosiphon causing convection flow between the inside of the vessel and the space defined by the casing.
摘要:
Magnetic actuators with dogs for positioning regulating rods in a nuclear reactor. The dogs (2) for lifting and/or holding the control shaft (1) are provided with at least two teeth (4) separated by a distance equalling that separating two successive grooves (3) of the shaft (1).
摘要:
Nuclear reactor safety rod release apparatus comprises a ring which carries detents normally positioned in an annular recess in outer side of the rod, the ring being held against the lower end of a drive shaft by magnetic force exerted by a solenoid carried by the drive shaft. When the solenoid is de-energized, the detent-carrying ring drops until the detents contact a cam surface associated with the lower end of the drive shaft, at which point the detents are cammed out of the recess in the safety rod to release the rod from the drive shaft. In preferred embodiments of the invention, an additional latch is provided to release a lower portion of a safety rod under conditions that may interfere with movement of the entire rod.
摘要:
A control rod drive attaching and detaching device and a control rod drive handling device are mounted on a revolving device to be movable independently from each other. The control rod drive attaching and detaching device includes bolt handling means for loosening and tightening bolts for fastening a control rod drive to a pressure vessel of a nuclear reactor, coolant splash preventing means for disposing of coolant which flows from the control rod drive when the latter is detached from the pressure vessel, and uncoupling means for uncoupling a control rod from the control rod drive. The control rod drive handling device includes a column pivotally mounted on a carriage, a cart removably mounted on the column, and means for moving the column to a horizontal position. Each control rod drive mounted to the pressure vessel of the nuclear reactor is detached from the pressure vessel by the control rod attaching and detaching device and transferred to the cart of the control rod drive handling device. The column is moved to a horizontal position, and the cart with the control rod drive supported thereon is removed from the column.