132 results about "Hot cell" patented technology

The invention belongs to the technical field of photo-thermal performance detection of building envelope structures, and particularly relates to a device and a method for detecting a solar heat gain coefficient under dynamic meteorological conditions of door and window curtain walls. The invention discloses a device for detecting a solar heat gain coefficient under a door and window curtain wall dynamic meteorological condition, and the device comprises an outdoor environment simulation hot chamber which comprises a solar radiation simulation system, a wind speed simulation system, and a temperature and humidity simulation system; an environmental space; the heat metering box and the outdoor environment simulation hot chamber are arranged in the horizontal direction, and the heat metering box is located in the environment space; a tested piece is arranged at the joint interface of the outdoor environment simulation hot chamber and the heat metering box along the vertical direction; the solar radiation simulation system adjusts the solar radiation intensity according to the received dynamic meteorological conditions, the wind speed simulation system adjusts the wind speed according to the received dynamic meteorological conditions, and the temperature and humidity simulation system adjusts the temperature and humidity according to the received dynamic meteorological conditions. According to the invention, the detection precision of the adjustable light-transmitting enclosure structure can be improved.

The invention discloses a hot chamber high-voltage electrical penetration assembly composite stress aging state evaluation method and a test device, and relates to the technical field of electrical equipment aging tests, and the method specifically comprises the steps: synchronously obtaining the leakage current, the partial discharge amplitude spectrum, the temperature distribution matrix and the high-frequency current spectrum of a to-be-tested electrical penetration assembly; extracting a time domain feature from the leakage current, extracting a frequency domain feature from the partial discharge spectrum, and extracting a space gradient feature from the temperature field; carrying out weighted fusion on the time domain features, the frequency domain features and the spatial gradient features by adopting an attention mechanism; reducing the 128-dimensional features after the attention mechanism fusion to three-dimensional spatial features; processing the fused three-dimensional space characteristics by adopting a bidirectional long-term memory network to obtain a residual life prediction value of the electrical penetration assembly; judging the aging stage of the electrical penetration assembly according to the residual life prediction value; presetting an aging threshold value, and when the predicted aging stage exceeds the threshold value, automatically adjusting the temperature and humidity parameters of the environmental test box to a safe working condition; the method is used for solving the problem that a traditional evaluation result is inaccurate.

The embodiment of the invention relates to the technical field of electrolytic production, recovery or refining of metal through a molten liquid electrolytic method, in particular to molten salt electrolytic refining equipment suitable for a hot chamber and a method for recovering uranium metal in spent fuel through molten salt electrolytic refining. The cathode and cathode transfer device is used for transferring the cathode into the electrolytic heating device or transferring the cathode away from the electrolytic heating device; the anode and anode transfer device is used for transferring the anode into the electrolytic heating device or transferring the anode away from the electrolytic heating device; the electrolytic product scraping and collecting device is used for carrying out scraping treatment on the cathode and collecting scraped objects; the electrolytic heating device moving assembly is used for enabling the electrolytic heating device to be moved to the hoisting station; and the cathode conductive device is connected with the cathode so as to electrify the cathode. According to the device provided by the embodiment of the invention, the electrolytic reaction can be continuously carried out, and the treatment requirement of the spent fuel is met.

The utility model relates to a high-efficiency air supply and exhaust device of an artificial nuclear medicine split charging hot chamber cabinet. The air supply and exhaust efficiency is improved. Comprising an air supply and exhaust top chamber and a shielding sub-packaging middle heat chamber shielding in-out lower heat chamber which is respectively provided with a sealing protection front door, a static pressure air supply box and an exhaust fan box which are arranged in the air supply and exhaust top chamber in parallel are respectively downwards communicated with an air supply port close to the sealing protection front door at the upper part in the shielding sub-packaging middle heat chamber shielding in-out lower heat chamber through a non-return air supply pipeline; and an exhaust outlet which is far away from the sealing protection front door and is provided with an activated carbon filter at the lower part in the shielding split charging middle hot chamber and the shielding in-out lower hot chamber is downwards communicated through a non-return exhaust pipeline. The device has the advantages that the quality of exhausted air is guaranteed, air in the hot chamber is prevented from overflowing when the door is opened, and nuclide pollution of the air in the hot chamber can be kept at a reasonable low level through adsorption of internal circulating airflow.

The invention discloses a modular hot cell, and relates to the technical field of radiation experiments. The hot cell comprises: a base; a shielding body, wherein the shielding body is arranged on the base; the shielding body is arranged on the base, the shell is arranged on the base, and the shell is located in the shielding body; part of the passing assembly is arranged on the shielding body, and part of the passing assembly is arranged on the shell; a part of the observation assembly is arranged on the shielding body, and a part of the observation assembly is arranged on the shell. According to the modularized hot chamber, through the modularized splicing structure of the base, the shielding body and the shell, the construction efficiency of the hot chamber is remarkably improved, the nested design of the shielding body and the shell forms a multiple radiation protection barrier, and the radiation leakage amount is controlled to be at an extremely low level while the operation visibility of personnel is guaranteed. According to the invention, a user can inspect the damaged fuel element at the first time, and the efficiency and reliability of fuel element damage inspection and analysis are improved.

The utility model discloses a hot chamber shell hauling platform which penetrates through a plant opening of a plant and comprises an external base station arranged on the outer side of the plant opening and an internal rack arranged on the inner side of the plant opening, and two hauling rails arranged in parallel are fixedly laid at the top ends of the external base station and the internal rack. Hauling tankette groups are respectively and correspondingly arranged in the two hauling tracks, and hauling power devices are respectively and fixedly arranged at the end parts of the two hauling tracks on the built-in rack; during use, the hot chamber shell is hoisted to the hauling tankette group outside a workshop opening, the hauling power device is hooked on the hot chamber shell, the hauling power device is started, and the hot chamber shell can be slowly and stably moved into the workshop by means of moving cooperation of the hauling tankette group. And hoisting equipment in the plant is used for hoisting and mounting in place, so that the in-place of the hot chamber shell is not limited by the construction period of the plant any more, the consignment in-place efficiency is high, and the construction period of the hot chamber is shortened.

The invention relates to the technical field of radioactive metal waste treatment, and provides radioactive metal waste smelting equipment which comprises a crucible and a desalting device, and the crucible comprises a split crucible used for containing radioactive metal waste; the desalting device comprises a collecting cavity communicated with the split crucible, the collecting cavity is located above the split crucible, and the collecting cavity is used for collecting salt substances evaporated in the heating process of the radioactive metal waste; wherein the crucible is detachably connected with the desalting device. The crucible is detachably connected with the desalting device, after smelting is finished, the crucible can be separated from the desalting device, and a metal ingot can be conveniently taken out from the crucible, so that the crucible can be disassembled, assembled, loaded and unloaded through remote operation such as a mechanical arm in a hot chamber environment, and the desalting device can be used for collecting salt substances and removing salt substances. And the device can be used for sealing the split crucible and can be used for sealing the split crucible, the structure is simplified, desalting, melting, alloying, curing and other functions are integrated, and the technological process is simplified.

A sterilization system for a radiopharmaceutical product comprising a hot cell disposed within a clean room environment. A sterilization shaft extends between a first end and a second end and defines an interior. The first end of the shaft is disposed within the hot cell and the second end of the shaft is disposed externally to the clean room. An electron beam accelerator assembly is disposed within the interior of the sterilization shaft so that an emission end of the electron beam accelerator is adjacent the first end of the sterilization shaft.

The utility model relates to the field of tellurium production of tellurium-zinc-cadmium purification, in particular to a distillation preposed preheating device for tellurium purification of tellurium-zinc-cadmium, which comprises a box body and a heating device, the box body comprises a front side plate, a rear side plate, a bottom plate and a top plate, a feed port is arranged on the front side plate, a discharge port is arranged on the rear side plate, and the heating device is arranged on the bottom plate. The bottom plate is provided with an S-shaped rail groove communicated with the feeding port and the discharging port, a first partition plate and a second partition plate are arranged in the box body and divide the interior of the box body into a first cavity, a second cavity and a third cavity, the heating device comprises a hot chamber, a burner, a draught fan and an air outlet pipe, the burner is communicated with the interior of the hot chamber, and the draught fan is communicated with the interior of the hot chamber. The air outlet pipe comprises a main pipe, a first branch pipe and a second branch pipe, the first branch pipe and the second branch pipe are communicated with the main pipe, the first branch pipe is communicated with the right side end of the first cavity, the second branch pipe is communicated with the left side end of the second cavity, the second branch pipe is connected with a third branch pipe, and the third branch pipe is communicated with the upper end of the third cavity. And the discharge port is rotationally connected with a second baffle plate.

The invention provides a preparation device of a heat source assembly. The heat source assembly includes a source core and a first enclosure including a first shell and a first cover. The preparation device comprises a rack, a measurement module, an assembly table, a welding module and a first transfer module. The measuring module is arranged on the rack and used for measuring the size of the source core. The assembling table is arranged on the rack, and a first shell is placed on the assembling table. The welding module is arranged on the rack and used for welding the assembled first shell and the first cover into a first cladding. And the first transfer module is movably arranged on the rack, and the first transfer module is used for transferring the measured source core into the first shell on the assembly table, assembling the first cover body and the first shell, and transferring the assembled first shell and the first cover body to the welding module. According to the preparation device, the automation degree of the preparation device can be improved, the production efficiency of the heat source assembly is improved, and the risk of large-scale radiation pollution on the surface of the hot chamber is reduced.

A system and method for producing radioisotopes such as molybdenum-99. The system comprises a first accelerator, a second accelerator, a first beamline, a second beamline, and a target. Using a pair of accelerators, beamlines are preferably fired at a target from opposite directions, thereby irradiating the target from both sides. The system can further comprise a target cooling system utilizing gaseous helium, a modular local target shielding comprised of boxes of either metal shot with liquid coolant or steel with concrete, and a hot cell for loading and unloading target disks.

The utility model discloses small-sized automatic code spraying and labeling equipment for a nuclear-grade environment. The small-sized automatic code spraying and labeling equipment comprises a label paper mounting module, a label paper guide module, a label paper position detection sensor, a label stripping module, a labeling module, a traction module and a waste paper collecting module. The device is small and compact in appearance size and can be shrunk and enlarged according to the size of label paper, and the hot chamber installation requirement is met; a transmission structure of the equipment adopts a synchronous belt for transmission, and the synchronous belt adopts a polyurethane steel wire belt for transmission, so that the equipment has certain radiation resistance; the bottom paper of the label is made of PVC, and the bottom paper is transparent, so that the label is convenient to detect and has certain strength and flexibility; the labeling module adopts a V-shaped unilateral moving design and can be compatible with bottles of different specifications; the whole equipment is made of a material with relatively high radiation resistance, so that the equipment has certain radiation resistance; parts of parts of the equipment are made of aluminum materials for weight reduction design, and the equipment is lighter than ordinary equipment.

The present application discloses a radiopharmaceutical synthesis and sub-packaging assembly line, which relates to the technical field of radiopharmaceutical preparation, including a synthesis hot chamber, a quality control chamber and a sub-packaging chamber for synthesizing a stock solution; the quality control chamber and the synthesis hot chamber are arranged side by side, and a first pipeline for transmitting the stock solution is arranged between the synthesis hot chamber and the quality control chamber, a running track and a detection equipment group for detecting the performance of the stock solution are arranged in the quality control chamber, and a filling bottle is detachably installed on the running track, and the filling bottle can move along the running track; the sub-packaging chamber is arranged on the side of the quality control chamber away from the synthesis hot chamber, and a second pipeline for transmitting the stock solution is arranged between the sub-packaging chamber and the quality control chamber. The present application has the effect of reducing the harm to the staff during the synthesis of radiopharmaceuticals.

The utility model relates to the technical field of hot chamber prefilters, in particular to a hot chamber prefilter which comprises a filter device, fixing rings are fixedly connected to the upper end and the lower end of the filter device, grooves are formed in the upper ends of the fixing rings, and cleaning rods are slidably connected to the adjacent ends of the two fixing rings. A plurality of evenly-installed brushes are arranged at the end, close to the filtering device, of the cleaning rod, connecting blocks are fixedly connected to the upper end and the lower end of the cleaning rod, a connecting rod is fixedly connected to the upper end of the connecting block located at the upper end, and a pushing block is fixedly connected to the upper end of the connecting rod; through the arrangement of the connecting rod, the cleaning rod, the brush and the fixing rod, equipment capable of being pushed to clean filtered impurities is additionally arranged on the outer side of an original filtering device, so that people can conveniently clean and maintain the filtering device when using the filtering device, and daily use of people is more convenient; and the practicability of the equipment in use is improved.

The present invention belongs to the technical field of spent fuel reprocessing, and specifically relates to a pulse backwash filtration device suitable for radioactive liquid, comprising a radioactive liquid feed section provided with a radioactive liquid storage tank (1) and a backwash water feed section provided with a backwash water storage tank (2), the radioactive liquid feed section and the backwash water feed section being respectively connected to a flocculation tank (3), the radioactive liquid feed section being able to filter the radioactive liquid sent from the flocculation tank (3) through the radioactive liquid storage tank (1) and then send it out, and the backwash water feed section being able to backwash the radioactive liquid storage tank (1) through the backwash water in the backwash water storage tank (2). The entire set of equipment of the present invention has no mechanical moving parts, is not easily damaged, has high reliability, is convenient to clean and maintain, and is suitable for installation in a radioactive hot cell.

This invention proposes a master-slave robotic arm control system and method for nuclear decommissioning operations. The system includes a data acquisition module that collects real-time posture data, corresponding communication delay data, and hot chamber environment data of the master and slave robotic arms; a data processing module that preprocesses the collected data, extracts standard feature information of the real-time posture of the master and slave robotic arms, standard feature information of the communication delay, and feature data of the hot chamber environment, and stores them in a motion information database; and a motion prediction module that constructs a trajectory prediction model for the slave robotic arm based on a neural network and outputs the predicted motion trajectory information of the slave robotic arm. In the nuclear decommissioning hot chamber environment, this system enhances the environmental adaptability of the system by collecting real-time posture data, communication delay data, and hot chamber environment data of the master and slave robotic arms, and combining them with a neural network to construct a high-precision trajectory prediction model for the slave robotic arm, thereby improving the accuracy and stability of the slave robotic arm in following the master arm's movements and ensuring precise synchronous operation of the master and slave robotic arms in complex environments.

A radiopharmaceutical dispensing device for controlling waste liquid splashing, relating to the technical field of radiopharmaceutical dispensing equipment, employs a shell, a protective support, and a retraction device. The shell has a notch on its side wall. The protective support is located at the notch and extends into the shell. The protective support includes two side plates and a base plate and a back plate disposed between the two side plates. The base plate, back plate, and two side plates form a side opening corresponding to the notch. The retraction device is disposed between the two side plates and includes a base on the base plate. A platform is slidably connected to the base, and the platform is equipped with an anti-tipping device. This invention allows the sliding platform to retract the waste liquid bottle into the protective support, preventing waste liquid from splashing into the protective support, avoiding contamination of the hot chamber, and eliminating safety risks. When the waste liquid bottle is full, it can be pulled out for easy replacement.

The utility model provides a power manipulator recovery mechanism and a nuclear decommissioning component dismantling device, and relates to the technical field of nuclear decommissioning treatment.The power manipulator recovery mechanism comprises a guide rail, a pushing piece, a pulling assembly and a connecting rope, the guide rail is horizontally arranged in a hot chamber, one end of the guide rail extends out of the hot chamber, and the guide rail is used for supporting a power manipulator to walk; the pushing piece is arranged on the guide rail in a sliding mode and located at the end, located in the hot chamber, of the guide rail, and the pushing piece is used for making contact with the power mechanical arm and pushing the power mechanical arm out of the hot chamber through the guide rail. According to the utility model, through the arrangement of the pulling assembly, when the power manipulator needs to be recycled, the connecting rope is wound through the pulling assembly, the pushing piece is driven to move on the guide rail, and the pushing piece pushes the power manipulator to move, so that the power manipulator is transferred from a hot chamber to an overhaul chamber; and the recovery operation of the power manipulator is completed.

A device converts a temperature difference into electric power by a Peltier element. The device includes at least one cold chamber closed by walls and at least one heat chamber open to the outside towards a heating-up area. The heat and cold chambers adjoin one another by one of these walls. This wall includes a Peltier element. A bell surrounds all cold chambers and heat chambers and separates the heating-up area from the external environment. At least three of the cold chambers each have the shape of a three-sided isosceles prism and touch each other at an axis of symmetry. The cold chambers are symmetrically distributed over 360°. At least three of the open heat chambers extend between the cold chambers. These cold and heat chambers form a first floor of the device. The walls have cooling fins on both sides of the walls.

The utility model relates to the technical field of tools, in particular to a quick-change tool for a sample clamp in a hot chamber, which comprises a machine body base, a machine body shell and a cutting component, wherein the machine body shell and the cutting component are arranged on the machine body base; a three-jaw chuck is detachably mounted at the end part of the rotating shaft through a quick release mechanism; the sliding block is controlled to be close to the clamp base through the bolt so that clamping force can be generated when a workpiece is clamped, the clamp base is a supporting structure of the clamp and can enable the clamp body to be kept stable when the clamp body is used, and when the bolt is tightened, the sliding block can extrude inwards to form the clamping force so that the workpiece can be clamped between the clamp base and the sliding block. The bolt achieves the purpose of clamping the workpieces by adjusting the distance between the clamp base and the sliding block, the clamp can clamp the workpieces of various shapes and sizes, high adaptability is achieved, the clamping force can be accurately controlled by adjusting the bolt, and different machining requirements are met.

The invention belongs to the technical field of radioactive hot cells, particularly relates to a radioactive hot cell of an intelligent control system and a working method of the radioactive hot cell, and aims to solve the problem that an existing radioactive hot cell lacks cleaning measures for medicine residues scattered on a tray. The inner wall of the notch is fixedly connected with an inner container, the inner wall of the bottom of the inner container is fixedly connected with an inner container tray, and the inner wall of the notch is connected with an isolation door through a hinge. According to the radioactive hot cell of the intelligent control system and the working method of the radioactive hot cell, after the radioactive drugs are prepared, drug residues scattered on the surface of the inner container tray in the hot cell body in a closed state can be cleaned in time; therefore, the influence of radioactive residues in the hot chamber body on subsequent medicine preparation is avoided, the harm of the residues to equipment or workers is reduced, the purity of the prepared medicine is improved, and the safety is improved.

The present invention relates to a laser transmission device and a laser transmission method, comprising a laser, a receiving module, a conducting module and an output module. The laser is used to generate a laser beam and output it to the receiving module through an armored cable. After receiving the laser beam output by the armored cable, the receiving module transmits the laser beam to the conducting module. The conducting module comprises a transmission section located inside a wall. The transmission section is used to transmit the laser beam received by the conducting module through at least a part of the wall. The output module is used to receive the laser beam transmitted by the conducting module and output the laser beam, thereby solving the problem of frequent replacement of the cutting head in the prior art. In addition, the laser transmission device arranges a laser that cannot withstand radiation outside the wall, thereby facilitating the protection and maintenance of the laser. The transmission section is used to transmit the laser from outside the hot room to inside the hot room. The optical path design is ingenious, which not only ingeniously solves the problem of spent fuel rod disintegration in the hot room, but also improves the efficiency of spent fuel rod disintegration.

The application provides a sample storage conveying system, which comprises a fixed frame, a heat accumulator fixedly installed on one side of the heat accumulator, mounting holes formed in the two sides of the fixed frame, an installation door hingedly connected to the inner wall surface of the mounting hole, and a semiconductor sample arranged in the fixed frame; and a temperature control assembly arranged in the fixed frame and used for controlling the temperature of the semiconductor sample. The fixed frame is composed of a heating chamber and a central isolation chamber and a cooling chamber, so that the heat carried by the conveying system between the heating chamber and the cooling chamber is reduced when the semiconductor sample is conveyed, thereby improving the practicability of the conveying system. The fan can be installed through the fixed hole, so that the conveying system can be circulated and cooled by the fan, air is blown from the lower structure, and air circulation is realized through a separate heat exchanger.

The present invention designs and develops a synthesis hot chamber system and synthesis method for the production of radioactive drugs. The synthesis hot chamber system includes a shielding box, an exhaust device, a fresh air device, a laminar flow device, a drug loading device, a radioactive drawer device, an activity well device, and a non-drawer device. The synthesis method is completed in the synthesis hot chamber system. The present invention adopts a Class A laminar flow design to ensure a clean environment for the production of radioactive drugs. In order to minimize the risk of personnel contact with radioactive materials, different transfer channels are designed in this patent for the transfer of radioactive and non-radioactive materials, and they are managed in different areas. Non-radioactive materials are transferred at the front of the shielding box to facilitate personnel operation, and radioactive materials are transferred at the back of the shielding box to reduce the risk of co-operators being irradiated.

The invention discloses an isotope production method of a pneumatic conveying type coating target material ball. The method comprises the following steps: putting a coating target ball into an absorption ball pore channel of a reflecting layer of a pebble-bed high-temperature gas cooled reactor for irradiation; after irradiation is completed, the coating target balls are conveyed back to the ball storage tank through a pneumatic conveying system; transferring the coated target balls after irradiation in the ball storage tank to a post-treatment hot chamber; and in a post-treatment hot chamber, dissolving and separating the coating of the coating target ball containing the target isotope to obtain a dissolving solution, and purifying the dissolving solution to obtain an isotope solution. Based on an existing secondary shut-down system engineering design scheme and a remote control technology, full-sealing and remote automatic operation of a target ball are achieved for isotope production, the risk that personnel make contact with radioactivity is reduced to the maximum extent, and normal power generation operation of the pebble-bed high-temperature gas cooled reactor is not affected.

The utility model relates to the technical field of manipulators, in particular to a special articulated manipulator for a hot chamber, which reduces the space occupation of the bottom of the hot chamber, has a simple structure, is convenient to mount and dismount, avoids being polluted and eroded, and has strong applicability. Comprising a multi-joint mechanical arm, a fixing assembly, a rotating assembly, a dismounting assembly and a protection assembly, the top of the multi-joint mechanical arm is installed at the top of a hot chamber through the fixing assembly, the rotating assembly is installed at the bottom of the fixing assembly, the output end of the rotating assembly is connected with the top of the multi-joint mechanical arm, and the dismounting assembly and an installation clamping component are installed at the bottom of the multi-joint mechanical arm; a protection assembly is installed outside the multi-joint mechanical arm.

A cell holder made up of a top tray, an intermediate tray and a frame. Cells are placed with minimal force in the frame to stand proud of it. The intermediate tray is placed over the projecting tops of the cells and serves to locate the cells. A busbar in the intermediate tray is connected to one set of terminals. A top tray is placed over the intermediate tray and snap-locked through the intermediate tray to the frame. The snap-lock distance is short. A busbar in the top tray is connected to the other set of terminals. The top tray shields the first busbar. Vents may be included to allow for the escape of hot cell gases in the event of failure.

The invention discloses a top cover of a transportation container and the container. The top cover comprises a cover body, a shielding piece and a locking piece. A pivoting space and a conveying channel are defined by the cover body, and in the first direction of the top cover, the conveying channel penetrates through the cover body and communicates with the pivoting space, and the conveying channel communicates with the containing space of the transportation container; the shielding piece is installed in the pivoting space in a pivoted mode, a communication hole penetrating through the shielding piece is formed in the peripheral wall of the shielding piece, the communication hole is suitable for being opposite to and communicating with the conveying channel and suitable for driving the shielding piece to rotate so that the shielding piece can communicate with or block the conveying channel, and the shielding piece is used for shielding nuclear radiation; the locking piece is arranged on the cover body and used for locking or unlocking the shielding piece. The shielding part is driven to rotate to block the conveying channel, an operator does not need to visually adjust the mounting position of the top cover, so that the loading efficiency of the nuclear spent fuel rod can be improved, the top cover is directly in butt joint with the hot chamber, then the shielding part is driven to rotate to open the conveying channel, and the operator can be prevented from being subjected to nuclear radiation as much as possible.

The utility model relates to container transfer technology field, concretely is a kind of multifunctional container transfer device, including base, still include: travelling mechanism, the travelling mechanism is set on base;Lifting mechanism, the lifting mechanism is set on the top of base;Uncovering mechanism, the uncovering mechanism is set on base, and the sealing cover compatible with the open upper end of container is connected in the execution end of uncovering mechanism;The utility model is by the cooperation of travelling mechanism, lifting mechanism, uncovering mechanism and sealing cover, constitute the multifunctional transfer device with moving, sealing, uncovering, lifting, not only can independently move in hot chamber, still can carry out plugging to the open upper end of container, effectively avoid the radioactive material splashing caused by vibration, jolt, greatly reduce hot chamber environment and equipment pollution risk;When reaching specified position, first remove sealing cover by uncovering mechanism, then utilize lifting mechanism to drive container to move upwards to complete height adjustment, save waiting link, greatly shorten operation cycle.