2979 results about "Control rod" patented technology

A device for gripping, holding, and releasing objects of varying sizes and shapes, which comprises an elongated torus (30) enclosing a fluid material (31), an external control rod (40), and an internal control rod (38). Torus (30) may be made of a flexible membrane and able to seal in fluid material (31). Fluid material (31) can be a gas, liquid, solid particles, semisolid particles, or mixtures of these. Central channel (34) of torus (30) is collapsed due to pressure of fluid material (31) within torus (30). Both control rods are securely attached to torus (30), with rod (38) attached to the interior portion of the torus along collapsed central channel (34), and rod (40) attached to the exterior portion of the torus on outer surface (32). Gripping action is achieved by differential linear motion of control rods (38) and (40) along the longitudinal (elongated) axis of torus (30). This causes front portion (36) of the torus to slide radially inward or outward to grip objects. Further movement of the control rods can cause the object to be pulled completely inside the collapsed channel for secure gripping by completely surrounding the object. The soft flexible nature of torus (30) allows grasping even the most delicate objects without damaging them. Even over-ripe strawberries can be rapidly grasped without bruising.

A control rod drive mechanism (CRDM) for use in a nuclear reactor, the CRDM comprising: a connecting rod connected with at least one control rod; a lead screw; a drive mechanism configured to linearly translate the lead screw; an electromagnet coil assembly; and a latching assembly that latches the connecting rod to the lead screw responsive to energizing the electromagnet coil assembly and unlatches the connecting rod from the lead screw responsive to deenergizing the electromagnet coil assembly. The latching assembly is secured with and linearly translates with the lead screw, while the electromagnet coil assembly does not move with the lead screw. The electromagnet coil assembly is at least coextensive with a linear translation stroke over which the drive mechanism is configured to linearly translate the lead screw.

A control rod drive mechanism (CRDM) comprises a lead screw, a motor threadedly coupled with the lead screw to linearly drive the lead screw in an insertion direction or an opposite withdrawal direction, a latch assembly secured with the lead screw and configured to (i) latch to a connecting rod and to (ii) unlatch from the connecting rod, the connecting rod being free to move in the insertion direction when unlatched, and a release mechanism configured to selectively unlatch the latch assembly from the connecting rod.

A silty floating mud collection device, which includes a drive cylinder, an outer sleeve, a sampler barrel, an lug cover plate, a turning cover, a control ring and a control rod, where the drive cylinder includes a cylinder liner, a piston and a piston rod; the outer sleeve is fixedly connected below the cylinder liner; the sampler barrel is detachably installed inside the outer sleeve; the lug cover plate is fixedly connected to a lower end of the piston rod, and can close an upper-end opening of the sampler barrel; the turning cover is turnably installed at a lower end of the outer sleeve, and can close a lower-end opening of the sampler barrel; the control ring is located below the sampler barrel, and is used to block the turning cover which is in an open state; and an upper end of the control rod is connected to the lug cover plate, and a lower end of the control rod is connected to the control ring.

RET antenna with motor and clutch assembly that is operative to mechanically disengage the DC motor and drive unit (also called the gear-motor unit) from the phase shifter adjustment shaft during a manual tilt operation. Disengaging the gear-motor unit removes the drag of the motor and the high gear ratio gear box from the phase shifter control rod making it easier to manually turn the phase shifter control knob. In addition, the clutch disengages the gear-motor without disengaging the position detector from the phase shifter control rod so that position calibration is not lost during manual tilt adjustment. When the manual tilt operation is completed, the mechanical tilt clutch enables the gear-motor unit to be reliably re-engaged with the phase shifter control rod for motorized electrical tilt operation without having to re-calibrate the position detector.

A spray head for fixing on a control rod of a valve or a pump. The spray head includes a body and a shutter disposed in a housing of the body. The housing is suitable for dispensing substance under pressure. At rest the shutter is in a closed position in which its frustoconical head portion is seated a frustoconical bearing surface of the body. The shutter moves away from the bearing surface under the pressure of the substance contained in the housing when the substance is being dispensed to form an annular dispenser orifice enabling the substance to be dispensed in the form of a hollow conical spray, at least in the vicinity of the spray head. The shutter moves away from the bearing surface against a resilient return action urging it back towards its closed position and returns to the closed position when the pressure of the substance diminishes.

A surgical stapling device particularly suited for endoscopic procedures is described. The device includes a handle assembly and an elongated body extending distally from the handle assembly. The distal end of the elongated body is adapted to engage a disposable loading unit. A control rod having a proximal end operatively connected to the handle assembly includes a distal end extending through the elongated body. A control rod locking member is provided to prevent movement of the control rod until the disposable loading unit is fully secured to the elongated body of the stapling device.

A safe, physically demanding interface device for children or other users to play video games according to the present invention includes a base and a joystick or control rod. The base supports a significant portion or the entirety of the child weight (e.g., supports a child in a seated or standing position), while the joystick is manipulable by the child to play the games. The device is configured to force the child to utilize many of the large muscle groups to interact with the game. Since the child weight is supported by the base, the interface device is stable (e.g., unlikely to tip or move) and, therefore, provides for safe, compelling video game play for users either alone or with other users.

The invention discloses an integral low-temperature nuclear heat reactor with the circuit equipment adopting integral arrangement and belonging to the low- and medium-parameter pressurized-water reactor, wherein, a reactor core adopts the mature nuclear power plant fuel component and control rod component; a main heat exchanger is of integral coil type; a voltage stabilizer is a built-in nitrogen partial pressure control voltage stabilizer; coolant circulation is completed by a built-in jet apparatus and the equipment of an external drive circuit; the drive circuit and the equipment and a main circuit auxiliary system are arranged at the circumference of a reactor pressure vessel; a containment vessel consists of a reactor body containment vessel and a reactor top containment vessel; the reactor body containment vessel which is a structure combined by a reactor vault of reinforced concrete structure and a casing of steel structure is connected with a sealed refueling water storage pool through a pipe and a valve. The thermal power of the reactor can be selected between 50MW and 500MW at will and the outlet temperature of the reactor can be selected between 100 DEG C to 200 DEG C according to application, requirement and power.

The invention relates to a precision vise used on a machine tool, the invention aims to solve the problems in the prior low speed moving vise where the operation is complicated and the working efficiency is low and in the prior high speed moving vise where the overspeed or overwearing and damage occur easily, the clamping accuracy is low and the service life is short; the invention adopts a novel structure of the double lateral locking and positioning, the technical proposal is that the invention consists of a vise base, a fixing vise jaw, a moving vise jaw and a quick moving mechanism, and is characterized in that a gear rack is arranged at the two sides of a vise base guiding rail, the quick moving mechanism consists of a nut base, a thrust screw rod and an expander, the expander consists of a pair of moving gear blocks, an expansion control rod and a reset spring, the outside of the moving gear blocks are respectively provided with a tooth row joggled with the tooth rack at the two sides of the vise base guiding rail, the expansion control rod matches with the moving gear block in driving manner, the expansion control rod matches with the nut base, the handholding end of which is arranged outside the nut base, the reset spring is connected with the two moving gear blocks, the thrust screw rod matches with the moving vise jaw, a flexible connection is adopted between the moving vise jaw and the quick moving mechanism.

Apparatus and method for varying field strength in a magnetic resonance system while keeping a relatively uniform magnetic field distribution. In an embodiment, a two-pole, generally u-shaped magnet assembly generates a static and uniform magnetic field. The magnet assembly includes two facing magnet poles separated by an air gap. Holes may be formed with the magnet poles. The field control rods may be placed at a pre-determined distance into these holes and symmetrically or asymmetrically moved across each magnet poles in a controlled manner to change the magnetic field strength while keeping the uniform magnetic field distribution. Maximum magnetic field strength may occur when the rods are removed. Minimum magnetic field strength may occur when the rods are fully inserted.

The invention discloses a test device of a model for manufacturing rock masses containing interlayers and a test method thereof. The test device of the model for manufacturing the rock masses containing interlayers comprises a semicircular angle device, an upper baffle, a lower baffle, a left side plate, a right side plate, a circular turntable, a core-drilling machine drill bit, a flat plate, a flat plate angle control rod, a fixed screw rod, a base plate, an interlayer model test piece, a U-shaped plate and a guide slot. The test method comprises the following test steps: arranging the rock masses according to an outline central line and fixing the rock masses; manufacturing interlayer materials and casting the model, fastening the test piece, drilling the core, replacing the core-drilling machine drill bit, changing the position of the test piece to drill repeatedly and cutting to obtain the test pieces with different height-diameter ratios or obtain the test pieces with different interlayer inclination angles; then carrying out mechanical test. The test device is simple in structure and suitable for manufacturing the test pieces with different interlayer thicknesses, inclination angles and height-diameter ratios; according to a core-drilling and cutting machining device, by making full use of the existing device, the influence on the mechanical properties of the test pieces caused by different conditions can be analyzed, coring of irregular rock samples taken in the site can be carried out directly, so that the test efficiency is improved and the test time is shortened.

The invention provides a combined square fuel assembly, a reactor core and a two-pass flowing method of a moderator and a coolant, which are suitable for a super-critical water reactor. The fuel assembly consists of 4 same child components arranged in a 2*2 square form, wherein each child component consists of multiple fuel rods arranged in a square grid form, a water rod is arranged in a central area, and a guide tube of a crossed control rod and a conduit of the water rod are placed above the component and a conduit of the water rod and a moderator duct are placed below the component; the reactor core is divided into first and second pass areas; the moderator flows into the space between the water rod and the child component from top to bottom in both passes; the coolant flows into a first pass fuel area from top to bottom; and the moderator and the coolant flow into a second pass fuel area from bottom to top after being stirred and mixed below the reactor core and flow out of the reactor core. According to the combined square fuel assembly, the reactor core and the two-pass flowing method of the super-critical water reactor, the moderator and the coolant as well as the different pass coolants in the components and the reactor core can be effectively shunted when the fuel rod is fully and uniformly moderated, the structural materials are reduced and the feasibility and safety are high.

A secure connection between the bottom nozzle of a nuclear fuel assembly and the control rod guide thimbles having two or four crimped pockets in the side wall of a bottom nozzle leg counterbore which are formed by drilling two or four blind holes through the top surface of the bottom nozzle. After attaching the bottom nozzle to the fuel assembly with a crimp bolt a pneumatic tool is then inserted into a flanged cup feature on the crimp bolt head and the flanged portion of the cup feature of the crimp bolt is deformed into the crimp pockets. The crimp pockets are contained within the leg counterbore and prevent the screw from rotating or falling out of the assembly in the event of preload loss or screw fracture.

A nuclear reactor includes a pressure vessel, and a control rod assembly (CRA) including at least one movable control rod, a control rod drive mechanism (CRDM) for controlling movement of the at least one control rod, and a coupling operatively connecting the at least one control rod and the CRDM. The coupling includes a connecting rod engaged with the CRDM and a terminal element connected with a lower end of the connecting rod and further connected with the at least one control rod. In some embodiments the terminal element includes a first portion comprising a first material having a first density and a second portion comprising a second material having a second density that is greater than the first density. In some embodiments the terminal element has a largest dimension parallel with the connecting rod that is greater than or equal to a largest dimension transverse to the connecting rod.

The invention relates to an exhaust brake with stable and adjustable operating pressure, stable brake and sensitive brake reaction, comprising a valve body, a disc, a supporting rod, a supporting sleeve, a control rod, a spring and an adjustable bolt without a pressure relief vent, wherein, the supporting rod and the supporting sleeve are used for fixing the disc, the control rod is used for controlling the on and off of an exhaust channel, the spring is used for adjusting the size of the operating back pressure of an assembly. The exhaust brake can release the excess pressure in time when the pressure surpasses the presetting value due to any unforeseen circumstances and guarantees the stable and reliable operating pressure; moreover, the exhaust brake with the decompressor has adjustable operating pressure, simple and convenient implementation and reliable performance.

The present invention is to provide a reactor core that allows a nuclear plant to continuously operate for a long term period, for example 15 years or longer, without requiring any fuel exchange, reduces the duration and number of maintenance steps involved in regular plant inspections, markedly improves plant availability and economic efficiency, and is effective in terms of nuclear nonproliferation.A plurality of fuel assemblies 103, themselves obtained by arranging fuel rods 100 and water rods 107 in square lattices, are arranged in a square lattice at a certain pitch. The blades 102a of a cross-shaped (cruciform) control rod 102 in a cross section are inserted into four adjacent spaces formed by four fuel assemblies 100 facing each other. A value of 0.06 cm−1 or greater is selected for the ratio (B / S) of the width (B) of each blade on the cruciform control rod 102 and the surface (S) of the fuel lattice defined by the surface area of a square whose side is equal to the pitch between the fuel assemblies 103.

A compact pressurised water nuclear reactor comprises a primary circuit fully integrated into the reactor vessel (10). Thus, a single steam generator (12) forms the cover of the vessel (10) and the pressuriser (30) and the primary pumps (28) are housed in the vessel (10). The same is true for the control mechanisms of the control rods (40). Finally, a venturi system (44) is also provided in the vessel (10) to create water circulation if there is a failure of the primary pumps (28).

The present invention is high pressure water jet perforating and auxiliary pressure fracturing method and apparatus. The apparatus includes a sheath, a releasing adaptor in the upper end of the sheath, a guiding pipe plug in the lower end, a piston inside the sheath, a wedge connected to the lower end of the piston, a ram head connected to the wedge, a jetting hose with nozzle in the top and connected to a core tube, a control rod connected to the hose and the sucker rod, an upper lock to limit the piston and a lower lock to limit the core tube. Compared with available technology, the present invention has the advantages of further greater treating depth, long and large perforation, increased drainage area and capacity, no contamination to perforation, simplified perforating and pressure fracturing process and saving in oil producing cost.