CN104376885A - Recycling device of light water coupling agent for supersonic inspection on heat transfer branch pipe of heavy water reactor power station - Google Patents

Recycling device of light water coupling agent for supersonic inspection on heat transfer branch pipe of heavy water reactor power station Download PDF

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Publication number
CN104376885A
CN104376885A CN201310348900.0A CN201310348900A CN104376885A CN 104376885 A CN104376885 A CN 104376885A CN 201310348900 A CN201310348900 A CN 201310348900A CN 104376885 A CN104376885 A CN 104376885A
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CN
China
Prior art keywords
water
power station
reactor power
heat transmission
transmission arm
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
Application number
CN201310348900.0A
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Chinese (zh)
Inventor
何海
商俊敏
王仕村
袁建中
杨崇安
陈明军
张志义
林百涛
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
CNNC Nuclear Power Operation Management Co Ltd
Third Qinshan Nuclear Power Co Ltd
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CNNC Nuclear Power Operation Management Co Ltd
Third Qinshan Nuclear Power Co Ltd
Priority date (The priority date 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 date listed.)
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Publication date
Application filed by CNNC Nuclear Power Operation Management Co Ltd, Third Qinshan Nuclear Power Co Ltd filed Critical CNNC Nuclear Power Operation Management Co Ltd
Priority to CN201310348900.0A priority Critical patent/CN104376885A/en
Publication of CN104376885A publication Critical patent/CN104376885A/en
Pending legal-status Critical Current

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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/28Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
    • GPHYSICS
    • G01MEASURING; TESTING
    • G01NINVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N29/00Investigating or analysing materials by the use of ultrasonic, sonic or infrasonic waves; Visualisation of the interior of objects by transmitting ultrasonic or sonic waves through the object
    • G01N29/22Details, e.g. general constructional or apparatus details
    • G01N29/28Details, e.g. general constructional or apparatus details providing acoustic coupling, e.g. water
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/017Inspection or maintenance of pipe-lines or tubes in nuclear installations
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/28Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
    • G21C19/30Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps
    • G21C19/307Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps specially adapted for liquids
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Health & Medical Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Chemical & Material Sciences (AREA)
  • Analytical Chemistry (AREA)
  • Biochemistry (AREA)
  • General Health & Medical Sciences (AREA)
  • General Physics & Mathematics (AREA)
  • Immunology (AREA)
  • Pathology (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention belongs to the technical field of nuclear station in-service inspection, and specifically relates to a recycling device of a light water coupling agent for the supersonic inspection on a heat transfer branch pipe of a heavy water reaction power station. The device comprises a water receiving disc, a water tank, a filter core, and a water pump. The wedge-shaped water receiving disc is inserted into a gap between fuel channels and is connected to one end of a recycled water soft pipe, the other end of the recycled water soft pipe is arranged above the filter core, the filter core is arranged in the water tank, the lower end of a water supply soft pipe is arranged in the water tank, and the upper end of the water supply soft pipe goes through the filter core and is connected to a supersonic inspecting probe through the water pump. The provided device can recycle a light water coupling agent, which is used in the supersonic inspection on a heat transfer branch pipe of a heavy water reaction power station. The provided device can reduce the surface pollution in the job site, reduce the amount of wetted thermal insulation cotton, and relieve the panic of non-staff members on the on-site water, when they have no idea on the on-site situation.

Description

Heavy water reactor power station Heat transmission arm ultrasonic examination light-water couplant retracting device
Technical field
The invention belongs to in-Service Inspection of Nuclear Power Station technical field, be specifically related to a kind of heavy water reactor power station Heat transmission arm ultrasonic examination light-water couplant retracting device.
Background technology
The reactor of CANDU6 type heavy water reactor power station is made up of 380 horizontally disposed fuel channels, the end of each fuel channel is connected to a Heat transmission arm, nuclear power station needs regularly to carry out inservice inspection (ultrasonic examination) to Heat transmission arm, ultrasonic examination needs to use light-water as couplant, light-water can along the outer wall of Heat transmission arm toward dirty, finally drenches the heat-preservation cotton of fuel channel bottom and flows to ground and cause excess surface water.Consider following four factors, need to reclaim light-water: the first, a large amount of light-waters can increase the load of reactor building vapor-recovery system, and tritium concentration in reactor building is raised.The second, a large amount of light-waters can make the heavy water of recovery demote.3rd, light-water drenches the heat-preservation cotton of fuel channel bottom, can increase the workload and collective dose of changing heat-preservation cotton.4th, the water that the personnel in nuclear island find scene is very responsive, is not that the member of this working group finds that light-water can produce unnecessary fear.At present, the ultrasonic examination of global CANDU6 type heavy water reactor power station Heat transmission arm does not reclaim light-water couplant.
Summary of the invention
The object of the invention is to a kind of heavy water reactor power station Heat transmission arm ultrasonic examination light-water couplant retracting device, the light-water couplant used in ultrasonic examination can be reclaimed, on-line filtration is carried out to the light-water reclaimed, recycles.
For achieving the above object, the technical solution used in the present invention is:
A kind of heavy water reactor power station Heat transmission arm ultrasonic examination light-water couplant retracting device, this device comprises drip tray, water tank, filter core, water pump; Wedge type drip tray inserts the gap between fuel channel, drip tray is connected with recycle-water flexible pipe one end, and the recycle-water flexible pipe other end is positioned at above filter core, and filter core is arranged in water tank, water supply hose lower end is arranged in water tank, and its upper end is connected with ultrasonic examining probe through water pump through filter core.
Described drip tray comprises framework, bearing, Qian Zui, clamping plate, elasticity rubber, water receiving ozzle, rubber peel, the front end of wedge type framework is front mouth, and the lower end of framework is connected with bearing, and elasticity rubber is between two laminated planks, its integral installation is on front mouth, and the upper edge of framework is provided with rubber peel; The lower weld of framework has water receiving ozzle.
The lower end of described framework is connected with bearing by bearing coupling bolt.
Described elasticity rubber is between two laminated planks, and its entirety is arranged on front mouth by elasticity rubber coupling bolt.
Described framework adopts aluminium alloy sheet weld to form.
The material of described bearing and clamping plate is polycarbonate.
Saddle type spring washer is adopted to seal between described bearing coupling bolt.
Gasket seal is adopted between described elasticity rubber coupling bolt.
Beneficial effect acquired by the present invention is:
The present invention can reclaim the ultrasonographic light-water couplant of heavy water reactor power station Heat transmission arm, thus reduce working site surface contamination, reduce by drench heat-preservation cotton quantity, alleviate inoperative group membership fear to on-the-spot water when ignorant.
Accompanying drawing explanation
Fig. 1 is heavy water reactor power station Heat transmission arm ultrasonic examination light-water couplant retracting device structural drawing of the present invention;
Fig. 2 is the drip tray structure figure of heavy water reactor power station Heat transmission arm ultrasonic examination light-water couplant retracting device of the present invention;
Fig. 3 is the drip tray front view of heavy water reactor power station Heat transmission arm ultrasonic examination light-water couplant retracting device of the present invention;
In figure: 1, drip tray; 2, water tank; 3, filter core; 4, water pump; 5, framework; 6, bearing; 7, Qian Zui; 8, clamping plate; 9, elasticity rubber; 10, water receiving ozzle; 11, rubber peel; 12, bearing coupling bolt; 13, elasticity rubber coupling bolt; 14, fuel channel; 15, calandria; 16, Heat transmission arm; 17, ultrasonic examining probe.
Embodiment
As shown in Figure 1, heavy water reactor power station Heat transmission arm ultrasonic examination light-water couplant retracting device of the present invention comprises drip tray 1, water tank 2, filter core 3, water pump 4; Wedge type drip tray 1 inserts the gap between fuel channel 14, drip tray 1 is connected with recycle-water flexible pipe one end, the recycle-water flexible pipe other end is positioned at above filter core 3, filter core 3 is arranged in water tank 2, water supply hose lower end is arranged in water tank, and its upper end is connected with ultrasonic examining probe 17 through water pump 4 through filter core 3;
As shown in figures 2-3, drip tray 1 comprises framework 5, bearing 6, front mouth 7, clamping plate 8, elasticity rubber 9, water receiving ozzle 10, rubber peel 11, the front end of wedge type framework 5 is front mouth 7, the lower end of framework 5 is connected with bearing 6 by bearing coupling bolt 12, elasticity rubber 9 is between two laminated planks 8, its entirety is arranged on front mouth 7 by elasticity rubber coupling bolt 13, and the upper edge of framework 5 is provided with rubber peel 11, and elasticity rubber 9 and rubber peel 11 are for preventing the outside surface damaging fuel channel 14; The lower weld of framework 5 has water receiving ozzle 10;
Gap between fuel channel 14 is irregular, in order to adapt to irregular space, drip tray 1 is designed to taper structure, and the front mouth 7 of drip tray can insert the gap of fuel channel 14, framework 5 adopts aluminium alloy sheet weld to form, and the material of bearing 6 and clamping plate 8 is polycarbonate; Saddle type spring washer is adopted to seal between bearing coupling bolt 12; Gasket seal is adopted between elasticity rubber coupling bolt 13.
Heat transmission arm 16 between fuel channel 14 mainly contains two kinds of arrangement forms, one is horizontally disposed, one is arranged vertically, the spatial joint clearance of two kinds of arrangement forms is different, for different arrangement form, mutually isostructural drip tray 1 can be adopted, but the length of drip tray 1 and width numerical value different, adjust according to actual needs.
During work, drip tray 1 is inserted the gap between fuel channel 14, reclaim ultrasonographic light-water, light-water is by water receiving ozzle 10, be back to water tank 2 through recycle-water flexible pipe again, the light-water of recovery after filter core 3 filters, then extracts supply ultrasonic examining probe 17 by water pump 4 and recycles.

Claims (8)

1. a heavy water reactor power station Heat transmission arm ultrasonic examination light-water couplant retracting device, is characterized in that: this device comprises drip tray (1), water tank (2), filter core (3), water pump (4); Wedge type drip tray (1) inserts the gap between fuel channel (14), drip tray (1) is connected with recycle-water flexible pipe one end, the recycle-water flexible pipe other end is positioned at filter core (3) top, filter core (3) is arranged in water tank (2), water supply hose lower end is arranged in water tank, and its upper end is connected with ultrasonic examining probe (17) through water pump (4) through filter core (3).
2. heavy water reactor power station Heat transmission arm ultrasonic examination light-water couplant retracting device according to claim 1, it is characterized in that: described drip tray (1) comprises framework (5), bearing (6), front mouth (7), clamping plate (8), elasticity rubber (9), water receiving ozzle (10), rubber peel (11), the front end of wedge type framework (5) is front mouth (7), the lower end of framework (5) is connected with bearing (6), elasticity rubber (9) is positioned between two laminated planks (8), its integral installation is on Qian Zui (7), the upper edge of framework (5) is provided with rubber peel (11), the lower weld of framework (5) has water receiving ozzle (10).
3. heavy water reactor power station Heat transmission arm ultrasonic examination light-water couplant retracting device according to claim 2, is characterized in that: the lower end of described framework (5) is connected with bearing (6) by bearing coupling bolt (12).
4. heavy water reactor power station Heat transmission arm ultrasonic examination light-water couplant retracting device according to claim 2, it is characterized in that: described elasticity rubber (9) is positioned between two laminated planks (8), its overall elasticity rubber coupling bolt (13) that passes through is arranged on front mouth (7).
5. heavy water reactor power station Heat transmission arm ultrasonic examination light-water couplant retracting device according to claim 2, is characterized in that: described framework (5) adopts aluminium alloy sheet weld to form.
6. heavy water reactor power station Heat transmission arm ultrasonic examination light-water couplant retracting device according to claim 2, is characterized in that: the material of described bearing (6) and clamping plate (8) is polycarbonate.
7. heavy water reactor power station Heat transmission arm ultrasonic examination light-water couplant retracting device according to claim 3, is characterized in that: adopt saddle type spring washer to seal between described bearing coupling bolt (12).
8. heavy water reactor power station Heat transmission arm ultrasonic examination light-water couplant retracting device according to claim 4, is characterized in that: adopt gasket seal between described elasticity rubber coupling bolt (13).
CN201310348900.0A 2013-08-12 2013-08-12 Recycling device of light water coupling agent for supersonic inspection on heat transfer branch pipe of heavy water reactor power station Pending CN104376885A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201310348900.0A CN104376885A (en) 2013-08-12 2013-08-12 Recycling device of light water coupling agent for supersonic inspection on heat transfer branch pipe of heavy water reactor power station

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201310348900.0A CN104376885A (en) 2013-08-12 2013-08-12 Recycling device of light water coupling agent for supersonic inspection on heat transfer branch pipe of heavy water reactor power station

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Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108088915A (en) * 2017-10-31 2018-05-29 中国大唐集团科学技术研究院有限公司火力发电技术研究所 A kind of non-destructive ultrasonic detects voussoir
CN109187753A (en) * 2018-10-15 2019-01-11 吉林大学 The supersonic detection device of face bonding fitting
CN109975415A (en) * 2017-12-27 2019-07-05 核动力运行研究所 A kind of trailing type couplant collection device for vertical vessel inner wall ultrasonic examination
CN113533536A (en) * 2021-07-22 2021-10-22 中广核检测技术有限公司 Nuclear power pipeline detection trace coupling water supply and recovery system

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4403510A (en) * 1980-10-23 1983-09-13 Dewalle Stewart Apparatus and method for ultrasonic inspection
CN85105453A (en) * 1985-07-17 1987-01-21 西屋电气公司 Ultrasonic non-destructive pipe testing system
CN101339163A (en) * 2008-08-14 2009-01-07 无锡东禾冶金机械厂 Steel cylinder supersonic flaw detecting machine
CN201873082U (en) * 2010-12-02 2011-06-22 核动力运行研究所 Coupling agent storage device for ultrasonic automatic inspection of pipe weld

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4403510A (en) * 1980-10-23 1983-09-13 Dewalle Stewart Apparatus and method for ultrasonic inspection
CN85105453A (en) * 1985-07-17 1987-01-21 西屋电气公司 Ultrasonic non-destructive pipe testing system
CN101339163A (en) * 2008-08-14 2009-01-07 无锡东禾冶金机械厂 Steel cylinder supersonic flaw detecting machine
CN201873082U (en) * 2010-12-02 2011-06-22 核动力运行研究所 Coupling agent storage device for ultrasonic automatic inspection of pipe weld

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108088915A (en) * 2017-10-31 2018-05-29 中国大唐集团科学技术研究院有限公司火力发电技术研究所 A kind of non-destructive ultrasonic detects voussoir
CN109975415A (en) * 2017-12-27 2019-07-05 核动力运行研究所 A kind of trailing type couplant collection device for vertical vessel inner wall ultrasonic examination
CN109975415B (en) * 2017-12-27 2024-04-09 核动力运行研究所 Following type couplant collecting device for ultrasonic inspection of inner wall of vertical container
CN109187753A (en) * 2018-10-15 2019-01-11 吉林大学 The supersonic detection device of face bonding fitting
CN113533536A (en) * 2021-07-22 2021-10-22 中广核检测技术有限公司 Nuclear power pipeline detection trace coupling water supply and recovery system

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Application publication date: 20150225