On-site implementation method for modification of in-service nuclear power station loading and unloading machine

Abstract

The invention relates to the field of nuclear power overhaul, in particular to a site implementation method for modifying an in-service nuclear power station loading and unloading machine. The method comprises the following steps of: confirming on-site implementation preconditions; hoisting upper reactor internals back to a reactor core, carrying out on-site arrangement before a loading and unloading machine is transformed, draining a reactor water pool, measuring original data, erecting a cart scaffold and opening an equipment valve; dividing areas, and transforming related parts; after main lifting system accessories are detached, an old upper tower, an old counterweight and an old lower tower are lifted away in sequence, a telescopic sleeve and a gripping apparatus are lifted away, and the upper tower, the counterweight and the lower tower are cleaned and decontaminated together with a low-span area of a reactor pool; the state of the fixed sleeve is checked, and an online blowing and sucking system is dismounted and mounted; synchronously replacing a power supply cabinet, a control cabinet and a gas circuit control cabinet and mounting a tower; terminating the cable and the gas pipeline; checking before power-on, and executing function and gas path pressure test after power-on is successful. Through modular disassembly and assembly and reasonable functional test sorting, the quality and progress of field implementation are ensured.

Description

Technical Field

[0001] The present invention relates to the field of nuclear power plant maintenance, and particularly to an implementation method for the renovation site of an in-service nuclear power plant's fuel handling machine. Background Art

[0002] For the refueling overhaul work of a pressurized water reactor nuclear power plant, the operation of loading and unloading nuclear fuel assemblies is required. The fuel handling machine, the only equipment in the nuclear island building for operating fuel assemblies, has malfunctioned in its functions many times due to failures of the grasping mechanism, lifting mechanism, trolley drive mechanism, operation control system, etc. The unreliability of this equipment directly increases the workload of on-site maintenance personnel and delays the progress of the main overhaul work, and at the same time poses a safety hazard to the operation of nuclear fuel assemblies.

[0003] Due to the particularity of the nuclear nature, the fuel handling machine is directly in contact with the fuel assemblies, and the equipment is located inside the nuclear island. During normal operation, personnel cannot enter for maintenance, and it cannot be replaced as a whole. Moreover, there are the following limiting conditions for the implementation of the renovation site of the fuel handling machine:

[0004] 1. Due to the requirements of equipment operation accuracy and core commissioning, the structure and interface form of the original trolley, carriage, track and fixed sleeve are retained in the renovation scope.

[0005] 2. The renovation implementation window of the fuel handling machine is set after the unit is shut down for overhaul and the nuclear fuel assemblies are unloaded from the core.

[0006] 3. The renovation of the fuel handling machine involves related specialties such as machinery, electricity, instrument control, lifting, scaffolding, operation, etc., and it is required that the safety, quality and progress of the whole renovation process are controllable.

[0007] 4. As the only available lifting equipment in the nuclear island building, the ring crane cannot perform two operations simultaneously during the implementation process, that is, the operations involving lifting and hoisting in the renovation implementation of the fuel handling machine can only be carried out step by step.

[0008] 5. The unit overhaul is irreversible. The renovation implementation process of the fuel handling machine is related to the unit overhaul conditions. It is necessary to combine the overhaul plan to determine the key points of the renovation implementation, and improve the control of the on-site implementation progress.

[0009] If the implementation method is unreasonable, it is easy to cause safety accidents or reduce the maintenance efficiency. Summary of the Invention

[0010] The technical problem to be solved by the present invention is: to provide an implementation method for the renovation site of an in-service nuclear power plant's fuel handling machine, which ensures the quality and progress of on-site implementation through modular disassembly and assembly and rationalized functional test sequencing, and ultimately improves the reliability and maintainability of the fuel handling machine operation.

[0011] The present invention provides an implementation method for the renovation site of an in-service nuclear power plant's fuel handling machine, including the following steps:

[0012] Step 1: Confirm the prerequisites for on-site implementation;

[0013] Step 2: Hoist the upper internals back into the core, move the refueling machine to the maintenance position, and then simultaneously carry out the on-site layout before the refueling machine transformation, drain the reactor pool, measure the original data, erect the gantry scaffold for the trolley, and open the equipment valves;

[0014] Step 3: After the refueling machine is powered off, divide the areas according to the different structural positions of the refueling machine and transform the relevant components;

[0015] Step 4: After the accessories of the main hoisting system are removed, hoist the old upper tower, counterweight, and lower tower away in sequence, hoist away the telescopic sleeve and the gripper, and clean and decontaminate the old telescopic sleeve after hoisting together with the low-span area of the drained reactor pool;

[0016] Step 5: After the decontamination and cleaning work of the reactor pool is completely completed, erect the scaffold for the fixed sleeve, and simultaneously check the status of the fixed sleeve and remove and install the on-line blowing and suction system;

[0017] Step 6: After the status check of the fixed sleeve is confirmed to be qualified, simultaneously replace the power cabinet, control cabinet, and gas circuit control cabinet and carry out the relevant installation of the tower;

[0018] At the same time, complete the termination of the cable and gas circuit pipelines, including the cable termination of the main hoisting, trolley, and car with the power cabinet, control cabinet, and junction box;

[0019] Step 7: Conduct a pre-power-on inspection of the refueling machine, and perform a function test and a gas circuit pressure test after successful power-on.

[0020] In a specific embodiment of the present invention, in the said Step 1, the said prerequisites include:

[0021] The ring crane is in a ready-to-use state at any time;

[0022] The feasibility and reliability of the functions of the performance transformation components of the refueling machine need to be verified in advance on the test platform;

[0023] All components involved in the on-site transformation of the refueling machine are disassembled into modular integrated components of the largest unit.

[0024] In a specific embodiment of the present invention, in the said Step 2, the said on-site layout includes the following steps in sequence:

[0025] Arrange anti-foreign object measures;

[0026] Power off the refueling machine.

[0027] In a specific embodiment of the present invention, in the said Step 2, after switching the unit operating condition to the drainage condition, drain the reactor pool;

[0028] When the water level reaches the flange surface of the pressure vessel, install a false top cover and carry out the cleaning and decontamination work in the high-span area. Continue to drain the water in the low-span area until the water level is not higher than 7.5 m and prepare for standby;

[0029] At the same time, the following operations are also carried out:

[0030] Open the equipment valve and carry out the transfer of the modified components of the charging and discharging machine;

[0031] Measure the original data of the charging and discharging machine;

[0032] Erect a scaffold on the gantry to remove the modified cables arranged on the gantry bridge, and remove the scaffold after completion.

[0033] In a specific embodiment of the present invention, step 3 specifically includes:

[0034] Remove the accessories of the main hoisting system;

[0035] Lift off the old control cabinet and the old power cabinet;

[0036] Remove the cables and gas pipelines of the gantry, repair the gantry drag chain, and lay new cables and gas pipelines;

[0037] Remove the cables and gas pipelines of the trolley, repair the trolley drag chain, and lay new cables and gas pipelines;

[0038] Remove the gantry encoder and camera, and replace them with new encoders and cameras after removal;

[0039] Remove the trolley encoder and camera, and replace them with new encoders and cameras after removal;

[0040] Remove and replace the anti-collision radar;

[0041] Remove and replace the junction box;

[0042] Remove and replace the in-situ protection proximity switch.

[0043] In a specific embodiment of the present invention, in step 6, the installation related to the tower includes: successively installing a telescopic sleeve and a gripper, a lower tower, a counterweight, an upper tower, and a main hoisting gas pipeline.

[0044] In a specific embodiment of the present invention, in step 7, the method for performing the function test is:

[0045] First, conduct an auxiliary protection function test;

[0046] Then, conduct a mechanical single test;

[0047] Next, conduct the remaining auxiliary protection function tests;

[0048] Complete the joint commissioning test of the equipment;

[0049] Conduct the dry simulation test of the charging and discharging machine;

[0050] Arrange the on-site state before the wet full simulation test of the charging and discharging machine, and conduct the automatic wet full simulation test of the charging and discharging machine.

[0051] In a specific embodiment of the present invention, the auxiliary protection function tests carried out first include, in sequence, the control system test, the encoder function test, the closed-circuit television system test, and the anti-collision function test;

[0052] The mechanical single-body tests specifically include: in sequence, the rotary positioning accuracy test, the repeat positioning accuracy test, the grab function test, the load test, and the manual emergency test;

[0053] The remaining auxiliary protection function tests specifically include: the fault alarm test, the interlock and bypass test, the operation area test, the boundary area test, and the core map test;

[0054] The dry simulation test of the discharging machine includes, in sequence, the manual dry simulation test, the automatic offset refueling dry test, the semi-automatic dry simulation test, and the full-automatic dry simulation test;

[0055] Completing the joint commissioning test of the equipment includes: the simulated core test, the trigger device test, the joint commissioning test of the transfer device, and the automatic positioning test of the tipping frame;

[0056] On-site state arrangement before the wet full simulation test of the charging and discharging machine: decontaminate the reactor pool, lift the dummy top cover, fill the reactor pool with water to the full water level state, and lift the upper in-core structure out of the core to the storage rack;

[0057] Conduct the automatic wet full simulation test of the charging and discharging machine, including, in sequence, the manual wet simulation test, the automatic offset refueling wet test, the semi-automatic simulated wet test, and the full-automatic simulated wet test.

[0058] In a specific embodiment of the present invention, the gas circuit pressure test is carried out simultaneously with the mechanical single-body test.

[0059] In a specific embodiment of the present invention, in step 5, the inspection of the state of the fixed sleeve includes the inspection of verticality and levelness.

[0060] Compared with the prior art, the on-site implementation method for the transformation of the charging and discharging machine of the in-service nuclear power plant of the present invention has the following beneficial effects:

[0061] (1) This method includes complete technical means for on-site implementation and functional testing of the transformation of the charging and discharging machine, achieving the effects of disassembling and assembling modular components of the equipment and meeting the on-site commissioning requirements.

[0062] (2) This method arranges and transforms the work items at different working conditions during the major overhaul of the unit, achieving the effect of reducing the workload of the loop low-low water level and accelerating the on-site implementation progress.

[0063] (3) This method divides the technical means of different working areas according to the structure of the refueling machine, achieving the effect of synchronously carrying out multiple transformation tasks that do not cross or interfere with each other and accelerating the on-site implementation progress.

[0064] (4) This method uses the technical means of the logical sequence of the functional test to achieve the effect of the reliability and stability of the operation of the refueling machine after transformation.

[0065] (5) This method transforms on the basis of the original trolley, carriage, track and fixed sleeve of the refueling machine, achieving the effect of the accuracy of the operation of the equipment after transformation. Description of the Drawings

[0066] Figure 1 Shows the flow of the on-site implementation method for the transformation of the refueling machine in an in-service nuclear power plant Figure 1 ;

[0067] Figure 2 Shows the flow of the on-site implementation method for the transformation of the refueling machine in an in-service nuclear power plant Figure 2 ;

[0068] Figure 1 and Figure 2 Is a complete flow chart. Due to space limitations, Figure 1 The pre-power-on inspection in Figure 2 Points to the gas circuit pressure test in Detailed Implementation Modes

[0069] To further understand the present invention, the implementation schemes of the present invention will be described below in conjunction with embodiments. However, it should be understood that these descriptions are only for further explaining the features and advantages of the present invention, rather than limiting the present invention.

[0070] The present invention only relates to the on-site implementation of the transformation of the refueling machine in an in-service nuclear power plant, including the content and logical sequence of the equipment transformation components and the functional test after transformation. The specific structure, connection and test methods are not within the protection scope of the present invention.

[0071] The transformation of the refueling machine is divided into two parts: mechanical and I&C modularization.

[0072] Among them, the mechanical part includes:

[0073] (1) The main hoisting system, including the upper tower, middle tower, telescopic sleeve, gripper, counterweight, auxiliary accessories;

[0074] (2) Pneumatic system, including overhead crane compressed air pipeline, trolley compressed air pipeline, pneumatic control cabinet, and main hoist compressed air pipeline;

[0075] (3) On-line blowing and suction system.

[0076] The instrument control part includes:

[0077] (1) Control cabinets, including control cabinet, power supply cabinet, and junction box;

[0078] (2) Encoder system, including overhead crane encoder and trolley encoder;

[0079] (3) Auxiliary protection system, including trolley cameras, anti-collision radar, and local protection proximity switches;

[0080] (4) Supporting cables, including overhead crane cables, trolley cables, main hoist cables, and main hoist cable tray.

[0081] An embodiment of the present invention discloses an implementation method for the on-site transformation of the refueling machine in an in-service nuclear power plant, as Figures 1 - 2 shown, including the following steps:

[0082] Step 1: Confirmation of on-site implementation prerequisites,

[0083] including: The ring crane is in a ready-to-use state;

[0084] The feasibility and reliability of the performance transformation components of the refueling machine need to be verified in advance on the test platform;

[0085] All components involved in the on-site transformation of the refueling machine are disassembled into modular integrated components with the largest units.

[0086] Step 2: Hoist the upper in-core structure back to the reactor core, run the refueling machine to the maintenance position, and then simultaneously carry out on-site layout before refueling machine transformation, drainage of the reactor pool, measurement of original data, erection of the overhead crane scaffolding, and opening of equipment valves;

[0087] The on-site layout includes the following steps in sequence:

[0088] Arrangement of anti-foreign object measures;

[0089] Power off the refueling machine.

[0090] Switch the full-water level condition of the unit overhaul, drain the reactor pool, and switch to the low-water level condition of the unit overhaul.

[0091] When the water level reaches the flange surface of the pressure vessel, install a false top cover, carry out cleaning and decontamination work in the high-span area, and continue to drain the low-span area until the water level is not higher than 7.5m for standby.

[0092] At the same time, also carry out:

[0093] Open the equipment valve and carry out the transfer of the modified parts of the loading and unloading machine;

[0094] Measure the original data of the loading and unloading machine;

[0095] Set up a scaffold on the trolley to remove the modified cables arranged on the trolley bridge, and then remove the scaffold after completion;

[0096] Step 3: After the loading and unloading machine is powered off, divide the areas according to the different structural positions of the loading and unloading machine, and modify the relevant components;

[0097] Specifically include:

[0098] Remove the accessories of the main hoisting system;

[0099] Lift off the old control cabinet and old power cabinet;

[0100] Remove the trolley cables and gas pipelines, repair the trolley drag chain, and lay new cables and gas pipelines;

[0101] Remove the hoist cables and gas pipelines, repair the hoist drag chain, and lay new cables and gas pipelines;

[0102] Remove the trolley encoders and cameras, and replace them with new ones after removal;

[0103] Remove the hoist encoders and cameras, and replace them with new ones after removal;

[0104] Remove and replace the anti-collision radar;

[0105] Remove and replace the junction box;

[0106] Remove and replace the in-situ protection proximity switch.

[0107] In the above transformation, the removal of the accessories of the main hoisting system is the main line, and the others are the secondary main lines. All supporting auxiliary equipment is preferably provided for the main line transformation.

[0108] Step 4: After the accessories of the main hoisting system are removed, lift off the old upper tower, balance weight and lower tower in sequence, lift off the telescopic sleeve and the gripper, and the old telescopic sleeve after being lifted off is cleaned and decontaminated together with the low-span area of the reactor pool after draining the water;

[0109] The telescopic sleeve and the gripper are lifted off as a whole component and carried out cleaning and decontamination together with the low-span area of the reactor pool, ensuring that the equipment meets the requirements of nuclear power plant radiation protection transfer and optimizing the main line work progress.

[0110] Step 5: After the decontamination and cleaning work of the reactor pool is completely finished, erect a fixed sleeve scaffold, and at the same time, conduct the inspection of the fixed sleeve status and the removal and installation of the on-line blowing and suction system;

[0111] The inspection of the fixed sleeve status includes the inspection of verticality and levelness.

[0112] The blowing and suction system includes a blowing pipeline and a suction pipeline.

[0113] Step 6: After the inspection of the fixed sleeve status is confirmed to be qualified, synchronously replace the power cabinet, control cabinet, and gas circuit control cabinet, and conduct the relevant installation of the tower crane;

[0114] The relevant installation of the tower crane includes: sequentially installing a telescopic sleeve and a gripper, a lower tower crane, a counterweight, an upper tower crane, and a main hoisting gas pipeline.

[0115] At the same time, complete the termination of cables and gas pipelines, including the cable termination of the main hoisting, trolley, and power cabinet, control cabinet, and junction box.

[0116] Step 7: Conduct the pre-power-on inspection of the charging and discharging machine. After the power-on is successful, perform the function test and the gas circuit pressure test.

[0117] The method of the function test is as follows:

[0118] First, conduct the auxiliary protection function test; specifically including: sequentially conducting the control system test, encoder function test, closed-circuit television system test, and anti-collision function test;

[0119] The control system test is the main line, and the rest are secondary main lines. Priority is given to ensuring the integrity of the control system function and improving the reliability of subsequent function tests.

[0120] Then, conduct the mechanical single-body test; specifically including: sequentially conducting the rotary positioning accuracy test, repeated positioning accuracy test, gripper function test, load test, and manual emergency test; at the same time, conduct the pressure test;

[0121] After the mechanical single-body test is completed, remove the fixed sleeve scaffold and hoist the simulated reactor core to the low-span area of the reactor pool.

[0122] Then, conduct the remaining auxiliary protection function tests: specifically including: fault alarm test, interlock and bypass test, operation area test, boundary area test, and reactor core map test. There is no sequence for the above tests.

[0123] Complete the equipment joint commissioning test, specifically including: simulated reactor core test, trigger device test, transfer device joint commissioning test, and tilting frame automatic positioning test; there is no sequence for the tests;

[0124] Conduct dry simulation tests on the charging and discharging machine, including successively carrying out manual simulation tests (dry), automatic offset refueling tests (dry), semi-automatic simulation tests (dry), and full-automatic simulation tests (dry);

[0125] On-site state arrangement before the full wet simulation test of the charging and discharging machine: Decontaminate the reactor pool, lift the false top cover, fill the reactor pool with water to 19.5 meters, and lift the upper in-core structure out of the core to the storage rack.

[0126] Conduct full wet simulation tests on the charging and discharging machine, including successively carrying out manual simulation tests (wet), automatic offset refueling method tests (wet), semi-automatic simulation tests (wet), and full-automatic simulation tests (wet).

[0127] The method of the present invention adapts to the on-site working conditions during the unit overhaul by setting key transformation nodes, and coordinates the quality and progress requirements of the charging and discharging machine transformation and the unit overhaul.

[0128] Key node one: Lift the telescopic sleeve and the grab component. Due to the radiation protection requirements of nuclear power plants, after the old telescopic sleeve is lifted, use the window for low-span drainage and decontamination of the reactor pool to synchronously carry out the flushing and cleaning of the telescopic sleeve.

[0129] Key node two: Confirm the state of the fixed sleeve. The fixed sleeve serves as the benchmark for the installation of the new tower and the telescopic sleeve, and is related to the qualification of the mechanical single-body test. After the original tower, telescopic sleeve, and counterweight are removed, check the verticality and levelness of the fixed sleeve. After meeting the requirements, proceed to the next step.

[0130] Key node three: Check cable terminations and power on the equipment. The transformation of the charging and discharging machine involves cable terminations for multiple discrete quantities, analog quantities, and communications. Check each cable of the charging and discharging machine on-site one by one to avoid rework and equipment damage caused by termination problems and ensure the transformation quality.

[0131] Key node four: Encoder function test. Implement the function tests of the encoders for the trolley, crab, and main hoist of the charging and discharging machine to ensure the operation accuracy of the charging and discharging machine and the quality of the mechanical single-body commissioning.

[0132] Key node five: Mechanical single-body test. The number of operators on the charging and discharging machine needs to be limited during the rotary positioning accuracy test and the repeated positioning accuracy test of the charging and discharging machine, and other tests are suspended. When the mechanical single-body test is qualified, the on-site cooperation scaffolding can be removed, and the charging and discharging machine can run at high speed in a waterless state except for the core area.

[0133] Key node six: Dry simulation test. When all the dry simulation tests of the charging and discharging machine are qualified, the unit overhaul can leave the low-low water level condition of the loop and enter the next stage of work.

[0134] The sorting of the functional tests after the transformation of the loading and unloading machine in the present invention is complete in terms of function verification and clear in logic, ensuring the normal operation of the equipment.

[0135] The present invention transforms the loading and unloading machine through modular disassembly and assembly and rational sorting of functional tests, ensuring the quality and progress of on-site implementation, and ultimately improving the reliability and maintainability of the operation of the loading and unloading machine.

[0136] The description of the above embodiments is only used to help understand the method and its core idea of the present invention. It should be noted that for those of ordinary skill in the art of this technology, without departing from the principle of the present invention, several improvements and modifications can be made to the present invention, and these improvements and modifications also fall within the protection scope of the claims of the present invention.

[0137] The above description of the disclosed embodiments enables those skilled in the art to implement or use the present invention. Various modifications to these embodiments will be obvious to those skilled in the art, and the general principles defined herein can be implemented in other embodiments without departing from the spirit or scope of the present invention. Therefore, the present invention will not be limited to these embodiments shown herein, but will be accorded the widest scope consistent with the principles and novel features disclosed herein.

Claims

1. A method for implementing on-site renovation of the refueling machine in an operating nuclear power plant, characterized in that, It includes the following steps: Step 1: Confirm the on-site implementation prerequisites; Step 2: Hoist the upper internals back into the core, move the refueling machine to the maintenance position, and then simultaneously carry out the on-site layout before the refueling machine transformation, drain the reactor pool, measure the original data, erect the scaffold for the trolley, and open the equipment valves; Step 3: After the refueling machine is powered off, divide the areas according to the different structural positions of the refueling machine and transform the relevant components; Step 4: After the accessories of the main hoisting system are removed, lift the old upper tower, counterweight, and lower tower away in sequence, lift away the telescopic sleeve and the gripper, and clean and decontaminate the old telescopic sleeve after lifting together with the low-span area of the drained reactor pool; Step 5: After the decontamination and cleaning work of the reactor pool is completely completed, erect the scaffold for the fixed sleeve, and at the same time check the state of the fixed sleeve and remove and install the on-line blowing and suction system; Step 6: After the state of the fixed sleeve is checked and confirmed to be qualified, simultaneously replace the power cabinet, control cabinet, and gas circuit control cabinet and carry out the relevant installation of the tower; At the same time, complete the termination of the cable and gas circuit pipelines, including the cable termination of the main hoisting, trolley, and car with the power cabinet, control cabinet, and junction box; Step 7: Conduct an inspection of the refueling machine before powering on the equipment. After successful power-on, perform the function test and the gas circuit pressure test.

2. The on-site implementation method for the modification of the refueling machine of an in-service nuclear power plant according to claim 1, characterized in that, In the said Step 1, the said prerequisites include: The ring crane is in a ready-to-use state at any time; The feasibility and reliability of the functions of the performance transformation components of the refueling machine need to be verified in advance on the test platform; All components involved in the on-site transformation of the refueling machine are disassembled into modular integrated components of the largest unit.

3. The method for on-site implementation of the modification of the refueling machine in an operating nuclear power plant according to claim 1, characterized in that In the said Step 2, the said on-site layout includes the following steps in sequence: Arrange the anti-foreign object measures; Power off the refueling machine.

4. The on-site implementation method for the modification of the refueling machine in an in-service nuclear power plant according to claim 3, wherein, In the said Step 2, after switching the unit operation condition to the drainage condition, drain the reactor pool; When the water level reaches the flange surface of the pressure vessel, install a dummy top cover, carry out the cleaning and decontamination work in the high-span area, and continue to drain the low-span area until the water level is not higher than 7.5 m and prepare for standby; At the same time, also carry out: Open the equipment valves and carry out the transfer of the refueling machine transformation components; Measure the original data of the refueling machine; Erect the scaffold for the trolley to remove the transformed cables arranged on the trolley bridge, and remove the scaffold after completion.

5. The on-site implementation method for the transformation of the refueling machine of an in-service nuclear power plant according to claim 1, characterized in that, The said Step 3 specifically includes: Remove the accessories of the main hoisting system; Lift away the old control cabinet and old power cabinet; Remove the trolley cables and gas circuit pipelines, repair the trolley drag chain, and lay new cables and gas circuit pipelines; Remove the car cables and gas circuit pipelines, repair the car drag chain, and lay new cables and gas circuit pipelines; Remove the trolley encoder and camera, and replace and install a new encoder and camera after removal; Remove the car encoder and camera, and replace and install a new encoder and camera after removal; Remove and replace the anti-collision radar; Remove and replace the junction box; Remove and replace the in-situ protection proximity switch.

6. The on-site implementation method for the modification of the refueling machine of an in-service nuclear power plant according to claim 1, characterized in that In the said Step 6, the said relevant installation of the tower includes: install the telescopic sleeve and the gripper, the lower tower, the counterweight, the upper tower, and the main hoisting gas circuit pipeline in sequence.

7. The on-site implementation method for the modification of the refueling machine of an in-service nuclear power plant according to claim 1, characterized in that, In the said Step 7, the method for performing the function test is: First, conduct the auxiliary protection function test; Then, conduct the mechanical single test; Then, conduct the remaining auxiliary protection function tests; Complete the joint commissioning test of the equipment; Conduct the dry simulation test of the charging and discharging machine; Arrange the on-site state before the wet full simulation test of the charging and discharging machine, and conduct the automatic wet full simulation test of the charging and discharging machine.

8. The on-site implementation method for the modification of the refueling machine in an operating nuclear power plant according to claim 7, characterized in that, The first auxiliary protection function tests include conducting the control system test, encoder function test, closed-circuit television system test, and anti-collision function test in sequence; The mechanical single-body tests specifically include: conducting the rotary positioning accuracy test, repeat positioning accuracy test, grapple function test, load test, and manual emergency test in sequence; The remaining auxiliary protection function tests specifically include: fault alarm test, interlock and bypass test, operation area test, boundary area test, and core map test; The dry simulation test of the discharging machine includes conducting the manual dry simulation test, automatic offset refueling dry test, semi-automatic dry simulation test, and full-automatic dry simulation test in sequence; Completing the joint commissioning test of the equipment includes: simulated core test, trigger device test, transfer device joint commissioning test, and tilting frame automatic positioning test; On-site state arrangement before the wet full simulation test of the charging and discharging machine: decontaminate the reactor pool, lift the dummy top cover, fill the reactor pool with water to the full water level state, and lift the upper in-core structure from the core to the storage rack; Conduct the automatic wet full simulation test of the charging and discharging machine, including conducting the manual wet simulation test, automatic offset refueling wet test, semi-automatic simulation wet test, and full-automatic simulation wet test in sequence.

9. The on-site implementation method for the modification of the refueling machine of an in-service nuclear power plant according to claim 7, characterized in that, The gas circuit pressure test is carried out simultaneously with the mechanical single-body test.

10. The method for on-site implementation of the modification of the refueling machine in an in-service nuclear power plant according to claim 1, characterized in that, In step 5, the inspection of the fixed sleeve state includes the inspection of perpendicularity and levelness.

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