CN109961858A - Underwater remote maintenance process for pressurized-water reactor nuclear power plant reactor core internals - Google Patents
Underwater remote maintenance process for pressurized-water reactor nuclear power plant reactor core internals Download PDFInfo
- Publication number
- CN109961858A CN109961858A CN201711404339.8A CN201711404339A CN109961858A CN 109961858 A CN109961858 A CN 109961858A CN 201711404339 A CN201711404339 A CN 201711404339A CN 109961858 A CN109961858 A CN 109961858A
- Authority
- CN
- China
- Prior art keywords
- underwater
- bolt
- tool
- component
- reactor
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- 238000000034 method Methods 0.000 title claims abstract description 52
- 238000012423 maintenance Methods 0.000 title claims abstract description 45
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 37
- 238000012545 processing Methods 0.000 claims abstract description 9
- 230000008439 repair process Effects 0.000 claims description 10
- 238000009760 electrical discharge machining Methods 0.000 claims description 9
- 238000003860 storage Methods 0.000 claims description 9
- 230000000694 effects Effects 0.000 claims description 8
- 239000000428 dust Substances 0.000 claims description 5
- 238000005286 illumination Methods 0.000 claims description 3
- 238000004055 radioactive waste management Methods 0.000 claims description 3
- 238000012790 confirmation Methods 0.000 claims description 2
- 239000002901 radioactive waste Substances 0.000 claims description 2
- 238000001914 filtration Methods 0.000 claims 1
- 230000006378 damage Effects 0.000 abstract description 4
- 230000002159 abnormal effect Effects 0.000 abstract description 3
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 abstract description 3
- 239000004327 boric acid Substances 0.000 abstract description 3
- 238000013461 design Methods 0.000 abstract description 3
- 238000009434 installation Methods 0.000 abstract description 3
- 239000002699 waste material Substances 0.000 abstract description 2
- 238000007689 inspection Methods 0.000 description 7
- 241000196324 Embryophyta Species 0.000 description 6
- 230000014759 maintenance of location Effects 0.000 description 4
- 230000005855 radiation Effects 0.000 description 2
- 238000010977 unit operation Methods 0.000 description 2
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 1
- 235000006506 Brasenia schreberi Nutrition 0.000 description 1
- 244000267222 Brasenia schreberi Species 0.000 description 1
- 235000008331 Pinus X rigitaeda Nutrition 0.000 description 1
- 235000011613 Pinus brutia Nutrition 0.000 description 1
- 241000018646 Pinus brutia Species 0.000 description 1
- 230000032683 aging Effects 0.000 description 1
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 description 1
- 229910052782 aluminium Inorganic materials 0.000 description 1
- 239000004411 aluminium Substances 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 229910052796 boron Inorganic materials 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 230000008878 coupling Effects 0.000 description 1
- 238000010168 coupling process Methods 0.000 description 1
- 238000005859 coupling reaction Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 239000002927 high level radioactive waste Substances 0.000 description 1
- 238000011065 in-situ storage Methods 0.000 description 1
- 238000000465 moulding Methods 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 238000010079 rubber tapping Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 239000000725 suspension Substances 0.000 description 1
- 238000013024 troubleshooting Methods 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/003—Remote inspection of vessels, e.g. pressure vessels
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/003—Remote inspection of vessels, e.g. pressure vessels
- G21C17/013—Inspection vehicles
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention belongs to the maintenance technique fields of presurized water reactor reactor core internals, it is particularly used for the underwater remote maintenance process of pressurized-water reactor nuclear power plant reactor core internals, purpose is to design a kind of maintenance process for presurized water reactor reactor core internals, the technique can be under the conditions of boric acid water shielding, high radioactivity component bolted on in-pile component is replaced in realization at a distance, and meets anti-foreign matter control and require, technique includes the locking destruction of bolt, dismounting, returns dress, dress is returned in the dismounting of component, it is checked after repairing, temporary and abnormal conditions the processing of waste.Technique of the present invention has been applied to center nuclear power operation the 12nd overhaul reactor hanging basket disc bolt rehablitation project of Co., Ltd 300MW unit at present, the overhaul upper-part in-reactor component PU plate dismounting for the first time of Fan family mountain 1,2# unit and new drive shaft installation project, two projects smoothly complete, and process rationality is effectively verified.
Description
Technical field
The invention belongs to the maintenance technique fields of presurized water reactor reactor core internals, and in particular to be used for pressurized-water reactor nuclear power plant
The underwater remote maintenance process of reactor core internals.
Background technique
Due to the peculiar property of core, after the operation of nuclear reactor unit, the components such as reactor core internals have high radioactivity.With
Unit continuous service, the in-pile component gradually aging in reactor pressure vessel under high temperature, high pressure, water impact operating condition, if
Standby reliability reduces, and needs to replace related components, repair.Components on in-pile component mostly use bolt to connect
Mode is connect, locking mode mostly uses mechanically deform locking mode or welded type check pin.
Due to the high radioactivity of operating unit reactor core, all lifting, maintenances for in-pile component are both needed in boric acid water screen
Lower completion is covered, routine maintenance means are not available.Trouble shooting involved in technique, bolt disassembly, part exchanging, junk
Inspection etc. is both needed in water, use special tool(s) remote-controlled operation after keeping in, shift, repairing.
Since nuclear power station generates foreign matter in core region, very big hidden danger can be caused to nuclear plant safety stable operation, even
Cause nuclear safety accident, and the foreign matter of core region is salvaged and its complicated, difficulty, so the maintenance work for in-pile component relates to
And tool need to carry out locking processing, and implement whole process and need to follow stringent anti-foreign matter control.
Since the repair quality of in-pile component is directly related to the nuclear safety of unit operation, so the control of repair quality,
Inspection after repairing is of crucial importance.Whole maintenance process should be at visible, controlled range.Currently, being applied under high radioactivity environment
Underwater lighting, camera system technology it is more mature, meet requirement.
The outstanding journey that is threaded through of bolt can not be destroyed as screw retention occurs, and thread biting locking can not hang the abnormal conditions such as stubborn, need to prepare
Emergency plan.The underwater spark erosion technique for being applied to underwater extraordinary maintenance at present is more mature, special by designing, processing
Electrode can realize the techniques such as imderwater cutting, reaming, meet the in-situ processing requirement of emergency condition.
To sum up, now it is badly in need of the maintenance process of complete set, is bolted high radioactivity zero applied to nuclear power station in-pile component
The replacement of component, the technique need to realize underwater remote-controlled operation, and meet anti-foreign matter control and require.
Summary of the invention
The purpose of the present invention is designing a kind of maintenance process for presurized water reactor reactor core internals, which can be in boron
Under the conditions of sour water shielding, high radioactivity component bolted on in-pile component is replaced in realization at a distance, and meets anti-foreign matter
Control requires, and locking destruction of the technique comprising bolt, returns dress at dismounting, and dress is returned in the dismounting of component, checks after repairing, and waste is kept in
And the processing of abnormal conditions.
The present invention is implemented as follows:
A kind of maintenance process for presurized water reactor nuclear reactor in-pile component, which mainly includes following content:
1. maintenance work confirms, this technique pertains only to the replacement of in-pile component screw coupling member, and other connection types are not
Within this processing range.
2. maintenance process, all operations are both needed to carry out in boric acid water, and refuelling pool need to have enough water shields, and heap
High radioactivity part after inner member and replacement need to meet radiation protection requirement apart from water surface minimum range.
3. in-pile component is hoisted to storage rack special or in reactor core, the operation such as on storage rack, after the completion of maintenance activity,
In-pile component is hung into back reactor core.
4. using underwater lighting and underwater photographic system, whole maintenance works are in visible, controllable state.
Since the repair quality of in-pile component is directly related to the nuclear safety of unit operation, so the control of repair quality,
Inspection after repairing is of crucial importance.Whole maintenance process should be at visible, controlled range.
5. mobile maintenance platform is arranged above in-pile component, dosage rate should meet radiation protection and want at inspection platform
It asks.Underwater lighting, camera system can be set up on platform, maintenance personal carries out all operations on platform.
6. tool assemble, and be accurately positioned on the component to need repairing, destruction, new spiral shell to connection screw retention
The locking installation of bolt.
(1) if screw retention uses mechanically deform locking mode, the underwater long distance for having precise locating function can be used
Bolt is positioned from dismantling device, is connected, destroys anti-loose structure by way of increasing outstanding stubborn torque.
(2) if screw retention use welded type check pin mode, can be used underwater spark erosion equipment and with it is locking
The adaptable electrode of structure, destroys anti-loose structure.Edm process need to use underwater dust suction, filter plant, prevent
Foreign matter or molecule influence water quality.
(3) mechanically deform formula anti-loose structure is used wait return the new component of dress, locking cap is preset on component in advance.Make
With the underwater remote mechanically deform anti-loosening locking tool with precise locating function, the locking setting of new bolt is completed.
7. the dismounting of bolt, disengagement, temporary and time dress
(1) bolt is removed using underwater remote disassembling tool, and is transported in temporary container and disengages.Tool has to spiral shell
The clamping of bolt, anti-dropout design prevent from removing, bolt falling in transport process
(2) bolt is disengaged from dismantling device, is kept in temporary container.
(3) bolt returns dress.New bolt is mounted on dismantling device head, is located in position to be installed, and outstanding twist is installed.
(4) if during disassembling bolts, bolt occurs and is killed with thread Pilot hole, underwater spark erosion equipment can be used
Bolt is cut off, and carries out bottom outlet processing in the original location.Simultaneously using underwater remote bottom outlet thread forming tool processes bottom outlet screw thread
Bottom outlet screw thread is cleared up.Process need to use underwater dust suction, filter plant, prevent foreign matter or molecule shadow
Xiangshui County's matter.
8. the dismounting of worn part, returning for temporary and new component fill
(1) using underwater remote clamping tool, the worn part for having removed connection bolt is clamped simultaneously from in-pile component
It removes.
(2) worn part is moved in temporary container, and is disengaged from clamping tool, deposited in temporary container.
(3) using underwater remote clamping tool, the new component of preset mechanically deform formula anti-loose structure is returned and is filled to heap
Inner member position to be installed.
9. repair quality inspection, inspection of foreign substance
After the completion of maintenance activity, using the underwater lighting of high radioactivity environment, camera system, video inspection is carried out to repair quality
It looks into, and confirms that maintenance process foreign generates.
10. having removed the radioactive waste that part and other maintenance process generate to be wanted according to nuclear power plant's Radioactive waste management
Ask transhipment, storage.
11. the description of relevant device involved in technique, tool, design requirement are as follows:
(1) in-pile component suspender
For nuclear power plant's existing equipment, it to be used for the handling of upper and lower part in-pile component.
(2) in-pile component storage rack
For nuclear power plant's existing equipment, stored for upper and lower part in-pile component.
(3) mobile maintenance platform
Nuclear power plant's existing equipment, such as fuel manipulator crane gantry, reactor core maintenance auxiliary suspension bridge.
(4) underwater lighting, camera system
Underwater lighting system include refuelling pool pool wall at fixed lighting apparatus and portable underwater illumination set
It is standby.Camera system includes Underwater Camera, lengthens aluminium bar, hanger and storage, playback equipment.Underwater lighting and picture pick-up device are equal
Underwater and high radioactivity environment requirement should be met.
(5) underwater remote bolt disassembly tool
The existing tool of nuclear power plant, for disassembling bolts, installation and the anti-untwisting of mechanically deform locking type in maintenance activity
The destruction of structure.It can underwater, remote-controlled operation.Has accurate positioning function, it can be achieved that the positioning of bolt, connection and outstanding twisting.Have
Bolt clamping function, prevents in transport process, bolt falling.
(6) underwater spark erosion equipment, electrode
Underwater spark erosion equipment, electrode are whole set procurement special equipment, for techniques such as imderwater cutting, moldings.
(7) underwater remote bottom outlet thread forming tool
The existing tool of nuclear power plant can underwater, remote-controlled operation for bottom outlet thread tapping in maintenance activity.
(8) underwater dust suction, filter plant
For whole set procurement equipment, processing operation is used under hydrous water, prevents that foreign matter or molecule influence water quality.
(9) underwater remote clamping tool
The existing tool of nuclear power plant, removal and returning for new component for worn part fill.It can underwater, remote-controlled operation.Have
Accurate positioning function, it can be achieved that the component in maintenance activity positioning, clamping and disengagement.
(10) underwater remote mechanically deform anti-loosening locking tool
The existing tool of nuclear power plant, the locking cap for mechanically deform formula anti-loose structure clamp, and complete to have returned the anti-of dress bolt
Pine setting.It can underwater, remote-controlled operation.
(11) container is kept under water
Temporary, transhipment for worn part in maintenance activity and other high-level wastes.
The beneficial effects of the present invention are:
Technique of the present invention has been applied to operation the 12nd overhaul of the Co., Ltd 300MW unit reaction of center nuclear power at present
Heap hanging basket disc bolt rehablitation project, overhaul upper-part in-reactor component PU plate is removed for the first time and new drive shaft is pacified for Fan family mountain 1,2# unit
Dress project, two projects smoothly complete, and process rationality is effectively verified.
Detailed description of the invention
Fig. 1 is a kind of process of underwater remote maintenance process for nuclear power station reactor inner member of the invention
Figure.
Specific embodiment
The present invention is described further with reference to the accompanying drawings and examples.
As shown in Figure 1, a kind of underwater remote maintenance process for pressurized-water reactor nuclear power plant reactor core internals, specifically
Include the following steps:
Step 1: maintenance work confirmation then can be performed if job content is the replacement that in-pile component is bolted components
This process flow.
Step 2: Job readiness
Step 2.1: all devices that this technique is related to, tool are in place and available at the scene.
Step 2.2: use mechanically deform formula anti-loose structure, preset locking cap wait return dress component it is machined complete
At.
Step 2.3: refuelling pool is in full water state, and pond illumination is good.
Step 3: in-pile component is hoisted on in-pile component storage rack (2) using in-pile component suspender (1), such as in heap
Core region repairs operation, this step can not execute.
Step 4: mobile maintenance platform (3) is moved to above in-pile component position to be repaired.
Step 5: underwater lighting, camera system (4) are set up on mobile maintenance platform (3), will keep in container under water
(11) it is put into refuelling pool bottom.
Step 6: it destroys worn part and connects screw locking structure.Locking mode is judged, if it is mechanically deform locking side
Formula executes step 6.1, if it is welded type check pin, executes step 6.2.
Step 6.1: old bolt is positioned, is connected using underwater remote bolt disassembly tool (5), it is outstanding by increasing
The mode for twisting torque destroys anti-loose structure.
Step 6.2: destroying anti-loose structure using underwater spark erosion equipment, electrode (6).Implementation process is inhaled using underwater
Dirt, filter plant (8) prevent that foreign matter or molecule influence water quality.
Step 7: the dismounting of old bolt is disengaged and is kept in.If screw thread is good, step 7.1,7.2 are executed, if screw thread
It kills, can not be successfully dismounting, execute step 7.3.
Step 7.1: old bolt being positioned, is connected using underwater remote bolt disassembly tool (5), screws out old spiral shell
Bolt.
Step 7.2: bolt is moved in temporary container (11) under water and disengaged.
Step 7.3: cutting off bolt using underwater spark erosion equipment, electrode (6), and carry out bottom outlet in the original location and add
Work.Using underwater remote bottom outlet thread forming tool (7) machined bottom screw thread and clear up.Process need to use underwater inhale
Dirt, filter plant (8) prevent that foreign matter or molecule influence water quality.
Step 8: using underwater remote clamping tool (9), worn part is clamped and is removed from in-pile component, is placed
It keeps in container (11) under water.
Step 9: using underwater remote clamping tool (9), the new component of preset mechanically deform formula anti-loose structure is returned
It is filled to in-pile component position to be installed.
Step 10: new bolt is installed into remote bolt disassembly tool (5) head under water, and is located at screw thread bottom
Kong Zhong, outstanding stubborn tool are installed in place bolt.
Step 11: using underwater remote mechanically deform anti-loosening locking tool (10), the folder of new bolt lock cap is completed
Tightly.
Step 12: using underwater lighting, camera system (4), carries out video check to repair quality, and confirm and repaired
Journey foreign generates.
Step 13: the Spent Radioactive for having removed that components and other maintenance process generate in container (11) will be kept under water
Object requires transhipment, storage according to nuclear power plant's Radioactive waste management.
Step 14: all gadgets, tool are cleared up in scene of resuming work.
Step 15: by in-pile component being hoisted to reactor core using in-pile component suspender (1), such as core region into
Row maintenance activity, this step can not execute.
Claims (1)
1. a kind of underwater remote maintenance process for pressurized-water reactor nuclear power plant reactor core internals, it is characterised in that: it has
Body includes the following steps:
Step 1: this work then can be performed if job content is the replacement that in-pile component is bolted components in maintenance work confirmation
Skill process；
Step 2: Job readiness
Step 2.1: all devices that this technique is related to, tool are in place and available at the scene；
Step 2.2: using mechanically deform formula anti-loose structure, preset locking cap fills the machined completion of component wait return；
Step 2.3: refuelling pool is in full water state, and pond illumination is good；
In-pile component: being hoisted on in-pile component storage rack by step 3 using in-pile component suspender, is such as carried out in core region
Maintenance activity, this step can not execute；
Step 4: mobile maintenance platform is moved to above in-pile component position to be repaired；
Step 5: setting up underwater lighting, camera system on mobile maintenance platform, and underwater temporary container is put into refuelling pool
Bottom；
Step 6: it destroys worn part and connects screw locking structure；Judge locking mode, if it is mechanically deform locking mode, holds
Row step 6.1 executes step 6.2 if it is welded type check pin；
Step 6.1: old bolt being positioned using underwater remote bolt disassembly tool, is connected, by increasing outstanding stubborn torque
Mode destroy anti-loose structure；
Step 6.2: using underwater spark erosion equipment, electrode breakages anti-loose structure；Implementation process uses underwater dust suction, filtering
Equipment prevents that foreign matter or molecule influence water quality；
Step 7: the dismounting of old bolt is disengaged and is kept in；If screw thread is good, step 7.1,7.2 are executed, if thread biting locking,
It can not be successfully dismounting, execute step 7.3；
Step 7.1: old bolt being positioned using underwater remote bolt disassembly tool, is connected, old bolt is screwed out；
Step 7.2: bolt is moved in temporary container under water and disengaged；
Step 7.3: cutting off bolt using underwater spark erosion equipment, electrode, and carry out bottom outlet processing in the original location；Use water
It remote bottom outlet thread forming tool processes bottom outlet screw thread and clears up down；Process need to use underwater dust suction, filter plant, prevent
Only generating foreign matter or molecule influences water quality；
Step 8: using underwater remote clamping tool, worn part is clamped and is removed from in-pile component, placed temporary under water
It deposits in container；
Step 9: using underwater remote clamping tool, the new component of preset mechanically deform formula anti-loose structure is returned and is filled to heap
Inner member position to be installed；
Step 10: new bolt is installed into remote bolt disassembly tool head under water, and is located in thread Pilot hole, is hanged
Stubborn tool is installed in place bolt；
Step 11: using underwater remote mechanically deform anti-loosening locking tool, the clamping of new bolt lock cap is completed；
Step 12: using underwater lighting, camera system, carries out video check to repair quality, and confirm that maintenance process is no different
Object generates；
Step 13: the radioactive waste of components and the generation of other maintenance process will have been removed in underwater temporary container according to core
Power plant's Radioactive waste management requires transhipment, storage；
Step 14: all gadgets, tool are cleared up in scene of resuming work；
Step 15: in-pile component is hoisted to reactor core using in-pile component suspender, is such as repaired in core region
Operation, this step can not execute.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201711404339.8A CN109961858A (en) | 2017-12-22 | 2017-12-22 | Underwater remote maintenance process for pressurized-water reactor nuclear power plant reactor core internals |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201711404339.8A CN109961858A (en) | 2017-12-22 | 2017-12-22 | Underwater remote maintenance process for pressurized-water reactor nuclear power plant reactor core internals |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN109961858A true CN109961858A (en) | 2019-07-02 |
Family
ID=67019221
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201711404339.8A Pending CN109961858A (en) | 2017-12-22 | 2017-12-22 | Underwater remote maintenance process for pressurized-water reactor nuclear power plant reactor core internals |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN109961858A (en) |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110828014A (en) * | 2019-11-08 | 2020-02-21 | 中核核电运行管理有限公司 | Nuclear reactor maintenance mobile platform and using method thereof |
| CN111805198A (en) * | 2020-07-20 | 2020-10-23 | 中国核动力研究设计院 | Disassembling method for spent fuel storage cadmium framework of nuclear power station |
| CN111805481A (en) * | 2020-07-20 | 2020-10-23 | 中国核动力研究设计院 | Cadmium-storage grid disassembling equipment for second-generation nuclear power station spent fuel |
| CN111843417A (en) * | 2020-07-24 | 2020-10-30 | 中国核动力研究设计院 | Remote dismantling process for indoor equipment with strong heat release |
| CN114708998A (en) * | 2022-03-16 | 2022-07-05 | 中国原子能科学研究院 | Transmission device capable of being detached remotely |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5864594A (en) * | 1995-04-18 | 1999-01-26 | Westinghouse Electric Corporation | Apparatus and method for replacing internal components in a nuclear reactor |
| US20040114704A1 (en) * | 2002-06-11 | 2004-06-17 | Gilles Morel | Device for positioning and axial alignment of a com ustible assembly and method and device for rearranging a positioning alignment |
| CN205380641U (en) * | 2015-09-02 | 2016-07-13 | 中核核电运行管理有限公司 | Can be used to processingequipment that processing under water possesses repetition accurate positioning function |
| CN106486177A (en) * | 2015-09-02 | 2017-03-08 | 中核核电运行管理有限公司 | One kind high radioactivity foreign body multifunctional ceiling extracting container and fishing process under water |
| CN106481634A (en) * | 2015-09-02 | 2017-03-08 | 中核核电运行管理有限公司 | A kind of subassembly of lock bolt for high radioactivity equipment and the locking technique of expansion chuck |
| CN110744492A (en) * | 2019-11-08 | 2020-02-04 | 中核核电运行管理有限公司 | Remote bolt dismantling and automatic grabbing tool and using method thereof |
-
2017
- 2017-12-22 CN CN201711404339.8A patent/CN109961858A/en active Pending
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5864594A (en) * | 1995-04-18 | 1999-01-26 | Westinghouse Electric Corporation | Apparatus and method for replacing internal components in a nuclear reactor |
| US20040114704A1 (en) * | 2002-06-11 | 2004-06-17 | Gilles Morel | Device for positioning and axial alignment of a com ustible assembly and method and device for rearranging a positioning alignment |
| CN205380641U (en) * | 2015-09-02 | 2016-07-13 | 中核核电运行管理有限公司 | Can be used to processingequipment that processing under water possesses repetition accurate positioning function |
| CN106486177A (en) * | 2015-09-02 | 2017-03-08 | 中核核电运行管理有限公司 | One kind high radioactivity foreign body multifunctional ceiling extracting container and fishing process under water |
| CN106481634A (en) * | 2015-09-02 | 2017-03-08 | 中核核电运行管理有限公司 | A kind of subassembly of lock bolt for high radioactivity equipment and the locking technique of expansion chuck |
| CN110744492A (en) * | 2019-11-08 | 2020-02-04 | 中核核电运行管理有限公司 | Remote bolt dismantling and automatic grabbing tool and using method thereof |
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110828014A (en) * | 2019-11-08 | 2020-02-21 | 中核核电运行管理有限公司 | Nuclear reactor maintenance mobile platform and using method thereof |
| CN111805198A (en) * | 2020-07-20 | 2020-10-23 | 中国核动力研究设计院 | Disassembling method for spent fuel storage cadmium framework of nuclear power station |
| CN111805481A (en) * | 2020-07-20 | 2020-10-23 | 中国核动力研究设计院 | Cadmium-storage grid disassembling equipment for second-generation nuclear power station spent fuel |
| CN111843417A (en) * | 2020-07-24 | 2020-10-30 | 中国核动力研究设计院 | Remote dismantling process for indoor equipment with strong heat release |
| CN111843417B (en) * | 2020-07-24 | 2021-08-03 | 中国核动力研究设计院 | Remote dismantling process for indoor equipment with strong heat release |
| CN114708998A (en) * | 2022-03-16 | 2022-07-05 | 中国原子能科学研究院 | Transmission device capable of being detached remotely |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN109961858A (en) | Underwater remote maintenance process for pressurized-water reactor nuclear power plant reactor core internals | |
| US6643349B2 (en) | Method of removing a large-sized apparatus from a reactor building of a nuclear plant | |
| JP3660770B2 (en) | How to replace in-furnace structures | |
| JP3679823B2 (en) | How to replace the core shroud | |
| CN106481634B (en) | A kind of subassembly of lock bolt and the locking technique of expansion chuck for high radioactivity equipment | |
| JP3897928B2 (en) | How to replace the core shroud | |
| JPS613090A (en) | Method and device for exchanging split pin aggregate of guide pipe | |
| JP2015049060A (en) | Fuel debris carry-out apparatus and carry-out method in boiling water nuclear power plant | |
| JP2006313134A (en) | Drum conceal type ion-exchange resin column | |
| JP3471295B2 (en) | How to replace core sparger | |
| JPH08233972A (en) | Method for replacing nuclear reactor internal constitution | |
| JP2766195B2 (en) | Reactor internal structure replacement method | |
| JPH06102398A (en) | Disposal method for reactor pressure vessel and its system | |
| CN209071003U (en) | A kind of irradiation blockage auxiliary disassembling tool | |
| JP2533622B2 (en) | Method of repairing neutron flux monitor housing | |
| JP4316130B2 (en) | Core spray system piping replacement method | |
| JP4393011B2 (en) | Replacement method of core spray system equipment | |
| JP2011169649A (en) | Nuclear reactor well gate and nuclear reactor inspection method | |
| JP2000304890A (en) | Reactor internal structure replacing method | |
| JPH08285997A (en) | Shielding method in replacement of reactor pressure vessel | |
| JP2000249791A (en) | Replacing method for reactor core shroud | |
| CN208433226U (en) | A kind of npp safety shell filtering emission system | |
| JPH10260290A (en) | Method and apparatus for replacing structure in reactor pressure vessel | |
| JP2000304892A (en) | Reactor internal structure replacing method | |
| Lipford et al. | Three mile Island revisited |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| CB03 | Change of inventor or designer information |
Inventor after: Nie Wenzhe Inventor after: Ni Yanfei Inventor after: Tao Lei Inventor after: Zhu Caijun Inventor after: Fan Weifeng Inventor after: Zhong Boling Inventor after: Guan Jianjun Inventor after: Qi Hongchang Inventor after: He Zijian Inventor after: Lu Shaowei Inventor after: Guo Liang Inventor before: Nie Wenzhe Inventor before: Ni Yanfei Inventor before: Tao Lei Inventor before: Zhu Caijun Inventor before: Fan Weifeng Inventor before: Zhong Boling Inventor before: Guan Jianjun Inventor before: Qi Hongchang Inventor before: He Zijian Inventor before: Lu Shaowei Inventor before: Guo Liang |
|
| CB03 | Change of inventor or designer information | ||
| RJ01 | Rejection of invention patent application after publication |
Application publication date: 20190702 |
|
| RJ01 | Rejection of invention patent application after publication |