CN113744905A - Real-time stress protection device and method for fuel assembly in third-generation nuclear power unit - Google Patents
Real-time stress protection device and method for fuel assembly in third-generation nuclear power unit Download PDFInfo
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- CN113744905A CN113744905A CN202110538561.7A CN202110538561A CN113744905A CN 113744905 A CN113744905 A CN 113744905A CN 202110538561 A CN202110538561 A CN 202110538561A CN 113744905 A CN113744905 A CN 113744905A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
- G21C19/10—Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements
- G21C19/105—Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements with grasping or spreading coupling elements
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention belongs to the technical field of nuclear power technology operation protection, and particularly relates to a device and a method for protecting stress of a fuel assembly in a third-generation nuclear power unit in real time. The device comprises a mechanical structure and a control structure; the mechanical structure of the device is arranged on a steel wire rope of a lifting mechanism of a loading and unloading machine and comprises a winding drum, a fixed pulley block, a load sensor, a balance beam, a balance weight, a telescopic sleeve, a gripping apparatus and a balance weight limiting device; the control structure of the device comprises a PLC controller, a first group of double relays, a safety relay, a second group of double relays, an emergency brake, a motor driver and a motor brake. The real-time stress protection device for the fuel assembly provided by the invention can be free from the limitation of nuclear power generating unit plant layout, and can effectively protect the fuel assembly operated on the loading and unloading machine from the force exceeding the allowable load. The weight of the counterweight of the protection system can be adjusted according to needs, and the protection load can be set to a reasonable value by matching with electric control setting.
Description
Technical Field
The invention belongs to the technical field of nuclear power technology operation protection, and particularly relates to a device and a method for protecting stress of a fuel assembly in a third-generation nuclear power unit in real time.
Background
Hua longyi is the advanced nuclear power plant who satisfies third generation nuclear power technical standard, and for original second generation or second generation nuclear power plant with, Hualongyi's an important technological improvement is that set up the fuel assembly atress real-time protection device that function further optimization, security further improve.
The fuel assembly is a nuclear fuel for a reactor surrounded by a zirconium outer shell. The construction is in the form of an elongated rod construction and therefore can only carry limited loads in the axial direction. If the load is too large, the structure of the outer shell of the fuel assembly is damaged or the fuel assembly is bent, and the fuel assembly cannot be used.
During the transportation of the fuel assemblies, the operating equipment may be subjected to unexpected loads due to equipment failure or malfunction. At this time, if a set of real-time monitoring and protecting equipment is not provided, the fuel assembly is subjected to excessive external force.
The handling machine used in the Hualongyi nuclear power station is a device for transferring fuel assemblies, and the device is a link which can be used in a fuel operation process in the nuclear power station. Due to the structure of the loading and unloading machine, the weight of the self-contained equipment on a lifting mechanism greatly exceeds the axially allowable specified value of the fuel assembly. In order to ensure that the axial force of the fuel assembly is always less than the allowable value during operation, a balance weight is added to a transmission chain ring of the lifting structure for protecting the fuel assembly.
In the field of nuclear power design and engineering construction, the technical scheme for realizing the safety protection of the fuel assembly transfer process mainly comprises the following two solutions:
the first solution is to reduce the self weight of the fuel assembly transfer device, so that the self weight of the hoisting tool is always smaller than the allowed value of the fuel assembly. The structure requires that the elevation of the operating points of the fuel at the reactor core and the transfer position is similar, and the transfer of the fuel assembly can be realized without a long lifting appliance. The technical scheme is related to factory layout and operation elevation, and once the process requirement is determined, whether the scheme of reducing the self weight can be adopted can be directly judged. This solution is the simplest to implement, but it must be implemented only if the plant layout is able to meet the requirements. In a third-generation nuclear power unit represented by Hualong I, because multiple factors including safety and economy need to be comprehensively considered in the plant layout of the nuclear power unit, a plant layout scheme meeting the requirements of a stress real-time protection device of a fuel assembly loading and unloading machine cannot be specially set.
The second solution is to install a spring at the lower part of the lifting mechanism of the loading and unloading machine to ensure that the bearing force can always balance part of the dead weight of the lifting tool. The structure needs to arrange a plurality of spring groups at the lower part of the hoisting mechanism for supporting the hoisting mechanism, and when the hoisting tool falls to the upper part of the fuel assembly, the springs can balance the dead weight of a part of the hoisting tool. This structure requires a load sensor to be provided under the spring for detecting a change in load. The structure is mainly concentrated on the lower part of the hoisting mechanism, but the hoisting mechanism cannot be completely kept horizontal due to inconsistent deformation of a plurality of groups of springs, and a balance mechanism is required to be arranged for keeping the horizontal. The availability and the reliability of the whole device can be influenced by excessive structures and parts, and the requirement of the response speed of the three-generation nuclear power unit represented by Hualong I for protecting the stress of the fuel assembly loading and unloading machine in real time is also not met.
Therefore, there is a need to develop a device and a method for protecting the stress of a fuel assembly in a third-generation nuclear power unit represented by hualong number one in real time, so as to protect the fuel assembly from being applied by external force in real time, not only can the protection of overload or underload caused by interference in the lifting process of the fuel assembly be completed, but also the weight of an operating device per se can be prevented from exceeding the allowable stress value of the fuel assembly, and further the safety of a loading and unloading machine is enhanced.
Disclosure of Invention
The invention aims to provide a device and a method for protecting a fuel assembly stressed in a third-generation nuclear power unit in real time, so that the fuel assembly operated on a loading and unloading machine is effectively protected from being stressed beyond an allowable load.
In order to achieve the purpose, the technical scheme adopted by the invention is as follows:
a fuel assembly stress real-time protection device in a third-generation nuclear power unit comprises a mechanical structure and a control structure;
the mechanical structure of the device is arranged on a steel wire rope of a lifting mechanism of a loading and unloading machine and comprises a winding drum, a fixed pulley block, a load sensor, a balance beam, a balance weight, a telescopic sleeve, a gripping apparatus and a balance weight limiting device;
the control structure of the device comprises a PLC controller, a first group of double relays, a safety relay, a second group of double relays, an emergency brake, a motor driver and a motor brake;
operating the fuel assembly through the telescopic sleeve and the gripping apparatus;
the device comprises a gripping apparatus and a telescopic sleeve;
the balance weight, the winding drum, the steel wire rope, the fixed pulley block and other self-contained parts to be hoisted form a movable pulley system;
the fixed pulley block is arranged at the fixed end position of the movable pulley system through a fixed end equipment support, and a load sensor is arranged on the fixed end equipment support and used for monitoring the change of a main lifting load;
guiding the balance weight to a required position through a fixed pulley block;
the steel wire rope is controlled to be in a tensioning state all the time through the balance weight;
when the counterweight triggers the counterweight limiting device, the winding drum stops running, so that the force borne by the fuel assembly is protected from exceeding an allowable value;
after the safety relay receives the control signal, the first group of double relays and the second group of double relays are controlled by redundancy design to simultaneously disconnect the power supply of the safety brake and the emergency brake, meanwhile, the safety relay sends a safety stop signal to the motor driver, and the motor driver executes a safety stop function to control the internal contracting brake of the motor brake;
after receiving the control signal, the PLC disconnects the power supply of the safety brake and the emergency brake through the two groups of output modules respectively, and sends a stop instruction to the motor driver to control the motor brake.
Further, the device for protecting the stress of the fuel assembly in the third generation nuclear power unit in real time is as follows: the PLC, the first group of double relays, the safety relay, the second group of double relays and the motor driver are arranged in the control cabinet and are controlled and operated through electric signals; the safety brake, the emergency brake and the motor brake are arranged on the hoisting mechanism and act on the winding drum.
Further, the device for protecting the stress of the fuel assembly in the third generation nuclear power unit in real time is as follows: the steel wire rope is of a parallel double-rope structure; the balance beam is in a triangular structure, two corners of the balance beam are respectively connected with the parallel double ropes of the steel wire rope, and the other corner of the balance beam is connected with the balance weight.
Further, the device for protecting the stress of the fuel assembly in the third generation nuclear power unit in real time is as follows: the function of the counterweight limiting device is to monitor the position of the counterweight, the counterweight limiting device is triggered when the counterweight reaches a set position, and the counterweight limiting device sends two paths of signals to the safety relay of the first interlocking circuit and the second interlocking circuit digital PLC controller.
A real-time protection method for stress of a fuel assembly in a third-generation nuclear power unit adopts the above real-time protection device for stress of the fuel assembly in the third-generation nuclear power unit, and comprises the following steps:
the method comprises the following steps: under the condition that the control structure works normally, a motor driver in the control structure drives a lifting mechanism to operate, a load sensor monitors a main lifting load in real time and compares the main lifting load with a set value, and whether the load applied to the fuel assembly exceeds the set value is judged;
step two: when the fuel assembly descends to a parking position, the weights of the telescopic sleeve and the gripping apparatus are applied to the fuel assembly, when the load sensor monitors that the main lifting load reaches a set value in real time, a first stopping process is executed, the PLC controller controls the safety brake and the emergency brake to be disconnected through the two groups of output modules respectively, and meanwhile, a stopping instruction is sent to the motor driver to control the motor brake to brake and stop the movement of the lifting mechanism;
step three: under the condition that the first stopping process is failed, a second stopping process is executed, the balance weight participates in actual load control, and the weight of the telescopic sleeve and the gripping apparatus is not controlled to be exerted on the fuel assembly completely through the self weight of the balance weight;
step four: and under the condition that the first stopping process and the second stopping process are failed simultaneously, the balance weight continuously descends until the balance weight triggers a balance weight limiting device to execute a third stopping process, and the balance weight limiting device simultaneously sends two signals to a safety relay of the first interlocking loop and a digital PLC controller of the second interlocking loop to stop the movement of the hoisting mechanism.
Further, according to the method for protecting the stress of the fuel assembly in the third-generation nuclear power unit in real time, in the first step, when the load sensor monitors that the main lifting load applied to the fuel assembly is larger than a set value in real time in the descending process of the fuel assembly, the balance weight does not participate in the control of the main lifting load.
Further, the method for protecting the stress of the fuel assembly in the third-generation nuclear power unit in real time comprises the fourth step of completing the first interlocking loop through a safety relay; after the safety relay receives the signal sent by the counterweight limiting device, the safety relay controls the first group of double relays and the second group of double relays to simultaneously disconnect the power supply of the safety brake and the emergency brake through redundancy design, and simultaneously the safety relay sends a safety stop signal to the motor driver, and the motor driver executes a safety stop function to control the band-type brake of the motor brake.
Further, the method for protecting the stress of the fuel assembly in the third-generation nuclear power unit in real time comprises the fourth step of completing the second interlocking loop through the PLC; after receiving the signal sent by the counterweight limiting device, the PLC controller disconnects the power supply of the safety brake and the emergency brake through the two groups of output modules respectively, and sends a stop instruction to the motor driver to control the motor brake.
The real-time stress protection device for the fuel assembly provided by the invention can be free from the limitation of nuclear power generating unit plant layout, and can effectively protect the fuel assembly operated on the loading and unloading machine from the force exceeding the allowable load. The weight of the counterweight of the protection system can be adjusted according to needs, and the protection load can be set to a reasonable value by matching with electric control setting.
Other beneficial effects further include:
1) the structure is simple and reliable, and the reaction speed is high in structure because the balance weight and the load are connected in series.
2) The change of the load is monitored in real time through the load sensor in the control, the action of limiting the counterweight through double-path control is adopted, and the control is reliable.
Drawings
FIG. 1 is a schematic diagram of a mechanical structure of a fuel assembly stress real-time protection device in a third-generation nuclear power unit;
FIG. 2 is a schematic diagram of a control structure of a real-time stress protection device for a fuel assembly in a third generation nuclear power unit.
In the figure: the device comprises a winding drum (1), a steel wire rope (2), a fixed pulley group (3), a load sensor (4), a balance beam (5), a balance weight (6), a telescopic sleeve (7), a gripping apparatus (8), a fuel assembly (9), a balance weight limiting device (10), a PLC (programmable logic controller) controller (11), a first group of double relays (12), a safety relay (13), a safety brake (14), a second group of double relays (15), an emergency brake (16), a motor driver (17) and a motor brake (18).
Detailed Description
The invention is described in detail below with reference to the figures and specific embodiments.
The invention relates to a real-time stress protection device for a fuel assembly in a third-generation nuclear power unit, which comprises a mechanical structure and a control structure;
as shown in fig. 1, the mechanical structure of the device is arranged on a steel wire rope 2 of a lifting mechanism of a loading and unloading machine, and comprises a winding drum 1, a fixed pulley block 3, a load sensor 4, a balance beam 5, a balance weight 6, a telescopic sleeve 7, a gripping apparatus 8 and a balance weight limiting device 10;
the control structure of the device comprises a PLC (programmable logic controller) 11, a first group of double relays 12, a safety relay 13, a second group of double relays 15, an emergency brake 16, a motor driver 17 and a motor brake 18;
the fuel assembly 9 is operated through the telescopic sleeve 7 and the gripper 8;
the hoisting parts of the device comprise a gripping apparatus 8 and a telescopic sleeve 7;
the balance weight 6, the winding drum 1, the steel wire rope 2, the fixed pulley block 3 and the lifted self-contained component form a movable pulley system;
in the movable pulley system, the counterweight 6 and the lifted self-contained component are connected in series, so that the structural response speed is high.
The fixed pulley block 3 is arranged at the fixed end position of the movable pulley system through a fixed end equipment support, and a load sensor 4 is arranged on the fixed end equipment support and used for monitoring the change of a main lifting load;
the balancing weight 6 is led to a required position through the fixed pulley group 3;
the steel wire rope 2 is controlled to be always in a tensioning state through the balance weight 6;
when the counterweight 6 triggers the counterweight limiting device 10, the reel 1 stops running, so that the force applied to the fuel assembly 9 is protected from exceeding the allowable value;
after receiving the control signal, the safety relay 13 controls the first group of double relays 12 and the second group of double relays 15 to simultaneously disconnect the power supply of the safety brake 14 and the emergency brake 16 through a redundancy design, meanwhile, the safety relay 13 sends a safety stop signal to the motor driver 17, the motor driver 17 executes a safety stop function, and controls the motor brake 18 to brake;
after receiving the control signal, the PLC controller 11 disconnects the power supplies of the safety brake 14 and the emergency brake 16 through the two sets of output modules, and simultaneously sends a stop instruction to the motor driver 17 to control the motor brake 18 to brake.
In the embodiment, the PLC controller 11, the first group of double relays 12, the safety relay 13, the second group of double relays 15 and the motor driver 17 are installed in the control cabinet and are controlled by electric signals; the safety brake 14, the emergency brake 16 and the motor brake 18 are arranged on the hoisting mechanism and act on the winding drum 1; the steel wire rope 2 is of a parallel double-rope structure; the balance beam 5 is of a triangular structure, two corners of the balance beam are respectively connected with the parallel double ropes of the steel wire rope 2, and the other corner of the balance beam is connected with the balance weight 6; the function of the counterweight limiting device 10 is to monitor the position of the counterweight 6, trigger the counterweight limiting device 10 when the counterweight 6 reaches a set position, and send two signals to the safety relay 13 of the first interlocking circuit and the digital PLC controller 11 of the second interlocking circuit by the counterweight limiting device 10.
A real-time protection method for stress of a fuel assembly in a third-generation nuclear power unit adopts the above real-time protection device for stress of the fuel assembly in the third-generation nuclear power unit, and comprises the following steps:
the method comprises the following steps: under the condition that the control structure works normally, a motor driver 11 in the control structure drives a lifting mechanism to operate, a load sensor 4 monitors a main lifting load in real time and compares the main lifting load with a set value, and whether the load applied to the fuel assembly 9 exceeds the set value is judged;
when the load sensor 4 monitors that the main lifting load applied to the fuel assembly 9 is larger than a set value in real time during the descending process of the fuel assembly 9, the balance weight 6 does not participate in the main lifting load control.
Step two: when the fuel assembly 9 descends to a parking position, the weight of the telescopic sleeve 7 and the gripping apparatus 8 is applied to the fuel assembly 9, when the load sensor 4 monitors that the main lifting load reaches a set value in real time, a first stopping process is executed, the PLC 11 controls the safety brake 14 and the emergency brake 16 to be disconnected in power supply through two groups of output modules respectively, and meanwhile, a stopping instruction is sent to the motor driver 17 to control the motor brake 18 to brake and stop the movement of the lifting mechanism;
step three: in case of failure of the first stopping process, a second stopping process is carried out, the counterweight 6 participates in the actual load control, by virtue of the own weight of the counterweight 6, the weight of the control telescopic sleeve 7 and the gripping apparatus 8 is not all exerted on the fuel assembly 9;
step four: and under the condition that the first stopping process and the second stopping process fail simultaneously, the balance weight 6 continues to descend until the balance weight 6 triggers the balance weight limiting device 10 to execute a third stopping process, and the balance weight limiting device 10 simultaneously sends two signals to the safety relay 13 of the first interlocking circuit and the second interlocking circuit digital PLC 11 to stop the movement of the hoisting mechanism.
The first interlock loop is completed through a safety relay 13; after receiving the signal sent by the counterweight limiting device 10, the safety relay 13 controls the first group of double relays 12 and the second group of double relays 15 to simultaneously disconnect the power supply of the safety brake 14 and the emergency brake 16 through redundancy design, meanwhile, the safety relay 13 sends a safety stop signal to the motor driver 17, the motor driver 17 executes a safety stop function, and the motor brake 18 is controlled to brake.
The second interlocking loop is completed through the PLC 11; after receiving the signal sent by the counterweight limiting device 10, the PLC controller 11 disconnects the power supply of the safety brake 14 and the emergency brake 16 through two sets of output modules, and sends a stop instruction to the motor driver 17 to control the motor brake 18 to brake.
By adopting the action of controlling the position limitation of the balance weight in a double-path way, the control reliability of the device can be further improved.
The real-time stress protection device for the fuel assembly provided by the invention can be free from the limitation of nuclear power generating unit plant layout, and can effectively protect the fuel assembly operated on the loading and unloading machine from the force exceeding the allowable load. And the counterweight weight can be adjusted as required, and the protection load can be set to a reasonable value by matching with the arrangement of the control structure.
Various modifications and alterations of this invention may be made by those skilled in the art without departing from the spirit and scope of this invention. It should be noted that the above-mentioned embodiments are only exemplary, and those skilled in the art can make various modifications and variations on the above-mentioned embodiments without departing from the scope of the invention. It will be appreciated by persons skilled in the art that the foregoing detailed description is provided for the purpose of illustrating the invention and is not to be construed as limiting the invention. The scope of the invention is defined by the claims and their equivalents.
Claims (10)
1. The utility model provides a fuel assembly atress real-time protection device among third generation nuclear power unit which characterized in that:
the device comprises a mechanical structure and a control structure;
the mechanical structure of the device is arranged on a steel wire rope (2) of a lifting mechanism of a loading and unloading machine and comprises a winding drum (1), a fixed pulley block (3), a load sensor (4), a balance beam (5), a balance weight (6), a telescopic sleeve (7), a gripping apparatus (8) and a balance weight limiting device (10);
the control structure of the device comprises a PLC (programmable logic controller) controller (11), a first group of double relays (12), a safety relay (13), a second group of double relays (15), an emergency brake (16), a motor driver (17) and a motor brake (18);
operating the fuel assembly (9) through the telescopic sleeve (7) and the gripper (8);
the self-contained components of the device comprise a gripping apparatus (8) and a telescopic sleeve (7);
the balance weight (6), the winding drum (1), the steel wire rope (2), the fixed pulley block (3) and other self-contained parts to be hoisted form a movable pulley system;
the fixed pulley block (3) is arranged at the fixed end position of the movable pulley system through a fixed end equipment support, and a load sensor (4) is arranged on the fixed end equipment support and used for monitoring the change of a main lifting load;
the balance weight (6) is led to a required position through the fixed pulley block (3);
the steel wire rope (2) is controlled to be in a tensioning state all the time through the balance weight (6);
when the counterweight (6) triggers the counterweight limiting device (10), the winding drum (1) stops running, so that the force borne by the fuel assembly (9) is protected from exceeding an allowable value;
after the safety relay (13) receives the control signal, the first group of double relays (12) and the second group of double relays (15) are controlled to simultaneously disconnect the power supply of the safety brake (14) and the emergency brake (16) through redundancy design, meanwhile, the safety relay (13) sends a safety stop signal to the motor driver (17), the motor driver (17) executes a safety stop function, and the motor brake (18) is controlled to be braked;
after receiving the control signal, the PLC (11) disconnects the power supplies of the safety brake (14) and the emergency brake (16) through the two groups of output modules respectively, and sends a stop instruction to the motor driver (17) to control the motor brake (18) to brake.
2. The device for protecting the stress of the fuel assembly in the third-generation nuclear power unit in real time as claimed in claim 1, is characterized in that: the PLC (11), the first group of double relays (12), the safety relay (13), the second group of double relays (15) and the motor driver (17) are arranged in the control cabinet and are controlled and operated through electric signals; the safety brake (14), the emergency brake (16) and the motor brake (18) are arranged on the hoisting mechanism and act on the winding drum (1).
3. The device for protecting the stress of the fuel assembly in the third-generation nuclear power unit in real time as claimed in claim 1, is characterized in that: the steel wire rope (2) is of a parallel double-rope structure; the balance beam (5) is of a triangular structure, two angles of the balance beam are respectively connected with the parallel double ropes of the steel wire rope (2), and the other angle of the balance beam is connected with the balance weight (6).
4. The device for protecting the stress of the fuel assembly in the third-generation nuclear power unit in real time as claimed in claim 1, is characterized in that: the function of the counterweight limiting device (10) is to monitor the position of the counterweight (6), when the counterweight (6) reaches a set position, the counterweight limiting device (10) is triggered, and the counterweight limiting device (10) sends two signals to a safety relay (13) of a first interlocking loop and a second interlocking loop digital PLC (11).
5. The device for protecting the stress of the fuel assembly in the third-generation nuclear power unit in real time as claimed in claim 1, is characterized in that: the PLC (11), the first group of double relays (12), the safety relay (13), the second group of double relays (15) and the motor driver (17) are arranged in the control cabinet and are controlled and operated through electric signals; the safety brake (14), the emergency brake (16) and the motor brake (18) are arranged on the hoisting mechanism and act on the winding drum (1); the steel wire rope (2) is of a parallel double-rope structure; the balance beam (5) is of a triangular structure, two angles of the balance beam are respectively connected with the parallel double ropes of the steel wire rope (2), and the other angle of the balance beam is connected with the balance weight (6); the function of the counterweight limiting device (10) is to monitor the position of the counterweight (6), when the counterweight (6) reaches a set position, the counterweight limiting device (10) is triggered, and the counterweight limiting device (10) sends two signals to a safety relay (13) of a first interlocking loop and a second interlocking loop digital PLC (11).
6. A real-time protection method for stress of a fuel assembly in a third-generation nuclear power unit adopts the real-time protection device for the stress of the fuel assembly in the third-generation nuclear power unit, which is characterized in that: the method comprises the following steps:
the method comprises the following steps: under the condition that the control structure works normally, a motor driver (11) in the control structure drives a lifting mechanism to operate, a load sensor (4) monitors a main lifting load in real time and compares the main lifting load with a set value, and whether the load applied to a fuel assembly (9) exceeds the set value is judged;
step two: when the fuel assembly (9) descends to a parking position, the weights of the telescopic sleeve (7) and the gripping apparatus (8) are applied to the fuel assembly (9), when the load sensor (4) monitors that the main lifting load reaches a set value in real time, a first stopping process is executed, the PLC (11) controls the safety brake (14) and the emergency brake (16) to be disconnected from the power supply through two groups of output modules respectively, and meanwhile, a stopping instruction is sent to the motor driver (17) to control the motor brake (18) to brake and stop the movement of the lifting mechanism;
step three: in case of failure of the first stopping process, a second stopping process is carried out, the balance weight (6) participates in the actual load control, and the weight of the telescopic sleeve (7) and the gripping tool (8) is controlled not to be completely applied to the fuel assembly (9) through the self weight of the balance weight (6);
step four: under the condition that the first stopping process and the second stopping process fail simultaneously, the balance weight (6) continues to descend until the balance weight (6) triggers a balance weight limiting device (10) to execute a third stopping process, and the balance weight limiting device (10) simultaneously sends two paths of signals to a safety relay (13) of a first interlocking loop and a second interlocking loop digital PLC (11) to stop the movement of the hoisting mechanism.
7. The method for protecting the stress of the fuel assembly in the third-generation nuclear power unit in real time as claimed in claim 6, characterized in that: in the first step, when the load sensor (4) monitors that the main lifting load applied to the fuel assembly (9) is larger than a set value in real time in the descending process of the fuel assembly (9), the balance weight (6) does not participate in the control of the main lifting load.
8. The method for protecting the stress of the fuel assembly in the third-generation nuclear power unit in real time as claimed in claim 6, characterized in that: in the fourth step, the first interlocking loop is completed through a safety relay (13); after receiving a signal sent by the counterweight limiting device (10), the safety relay (13) controls the first group of double relays (12) and the second group of double relays (15) to simultaneously disconnect the power supply of the safety brake (14) and the emergency brake (16) through redundancy design, and simultaneously the safety relay (13) sends a safety stop signal to the motor driver (17), and the motor driver (17) executes a safety stop function to control the motor brake (18) to brake.
9. The method for protecting the stress of the fuel assembly in the third-generation nuclear power unit in real time as claimed in claim 6, characterized in that: in the fourth step, the second interlocking loop is completed through a PLC (11); after receiving the signals sent by the counterweight limiting device (10), the PLC (11) disconnects the power supplies of the safety brake (14) and the emergency brake (16) through the two groups of output modules respectively, and sends a stop instruction to the motor driver (11) to control the motor brake (18) to brake.
10. The method for protecting the stress of the fuel assembly in the third-generation nuclear power unit in real time as claimed in claim 6, characterized in that: in the first step, when a load sensor (4) monitors that the main lifting load applied to a fuel assembly (9) is larger than a set value in real time in the descending process of the fuel assembly (9), the balance weight (6) does not participate in the control of the main lifting load;
in the fourth step, the first interlocking loop is completed through a safety relay (13); after receiving a signal sent by a counterweight limiting device (10), the safety relay (13) controls a first group of double relays (12) and a second group of double relays (15) to simultaneously disconnect a power supply of a safety brake (14) and an emergency brake (16) through a redundancy design, meanwhile, the safety relay (13) sends a safety stop signal to a motor driver (17), the motor driver (17) executes a safety stop function, and controls a brake of a motor brake (18); the second interlocking loop is completed through a PLC (programmable logic controller) (11); after receiving the signals sent by the counterweight limiting device (10), the PLC (11) disconnects the power supplies of the safety brake (14) and the emergency brake (16) through the two groups of output modules respectively, and sends a stop instruction to the motor driver (17) to control the motor brake (18) to brake.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110538561.7A CN113744905A (en) | 2021-05-18 | 2021-05-18 | Real-time stress protection device and method for fuel assembly in third-generation nuclear power unit |
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Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4886174A (en) * | 1987-05-20 | 1989-12-12 | Reel S A | Load compensating device for a handling machine and process for carrying out such compensation |
| JPH1090478A (en) * | 1996-09-10 | 1998-04-10 | Reel Sa | Operation control method for load compensation device and load compensation device thereof |
| FR2764591A1 (en) * | 1997-06-13 | 1998-12-18 | Framatome Sa | Load compensation system for a manipulator |
| CN2780706Y (en) * | 2005-03-16 | 2006-05-17 | 方圆集团有限公司 | Automatic balancing pair weight of elevator |
| CN101062748A (en) * | 2006-04-25 | 2007-10-31 | 里尔有限公司 | Load compensation device, in particular for a lifting apparatus |
| CN201330127Y (en) * | 2009-01-21 | 2009-10-21 | 中国核电工程有限公司 | A loading and unloading machine for grabbing fuel assembly |
| ITMI20110054A1 (en) * | 2011-01-20 | 2012-07-21 | Ansaldo Nucleare Spa | LOAD COMPENSATION DEVICE FOR A NUCLEAR FUEL ELEMENT HANDLING MACHINE |
-
2021
- 2021-05-18 CN CN202110538561.7A patent/CN113744905A/en active Pending
Patent Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4886174A (en) * | 1987-05-20 | 1989-12-12 | Reel S A | Load compensating device for a handling machine and process for carrying out such compensation |
| JPH1090478A (en) * | 1996-09-10 | 1998-04-10 | Reel Sa | Operation control method for load compensation device and load compensation device thereof |
| FR2764591A1 (en) * | 1997-06-13 | 1998-12-18 | Framatome Sa | Load compensation system for a manipulator |
| CN2780706Y (en) * | 2005-03-16 | 2006-05-17 | 方圆集团有限公司 | Automatic balancing pair weight of elevator |
| CN101062748A (en) * | 2006-04-25 | 2007-10-31 | 里尔有限公司 | Load compensation device, in particular for a lifting apparatus |
| CN201330127Y (en) * | 2009-01-21 | 2009-10-21 | 中国核电工程有限公司 | A loading and unloading machine for grabbing fuel assembly |
| ITMI20110054A1 (en) * | 2011-01-20 | 2012-07-21 | Ansaldo Nucleare Spa | LOAD COMPENSATION DEVICE FOR A NUCLEAR FUEL ELEMENT HANDLING MACHINE |
| EP2479761A2 (en) * | 2011-01-20 | 2012-07-25 | Ansaldo Nucleare S.p.A. | Load compensating device for a nuclear fuel element handling machine |
Non-Patent Citations (1)
| Title |
|---|
| 穆兆辉: "PMC系统换料机整体设计和传输系统改造", 《中国优秀博硕士学位论文全文数据库(硕士)工程科技Ⅱ辑》 * |
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Application publication date: 20211203 |