CN107093471B - Protect the protection structure and its guard method of in-pile instrument line - Google Patents
Protect the protection structure and its guard method of in-pile instrument line Download PDFInfo
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- CN107093471B CN107093471B CN201710321599.2A CN201710321599A CN107093471B CN 107093471 B CN107093471 B CN 107093471B CN 201710321599 A CN201710321599 A CN 201710321599A CN 107093471 B CN107093471 B CN 107093471B
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- support column
- instrument line
- upper support
- pile instrument
- sleeve
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C11/00—Shielding structurally associated with the reactor
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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
Abstract
The invention discloses the protection structures and its guard method of protection in-pile instrument line; protect the protection structure of in-pile instrument line; upper support column including belonging to upper-part in-reactor component; it further include the sleeve part for protecting in-pile instrument line; during nuclear reactor works; sleeve part is located in upper support column, and in-pile instrument line is located in sleeve part；It is characterized in that, during nuclear reactor is safeguarded, in-pile instrument line is static relative to upper support column and is integrally promoted with portion's in-pile component, upper support column, and described sleeve pipe part can pass through the upward support column lower section free movement in upper support column lower end and cover the end of in-pile instrument line.
Description
Technical field
It is that in-pile instrument provides the structural member of protection and shielding the present invention relates to nuclear reactor in-pile component is belonged to, specifically
For be protect in-pile instrument line protection structure and its guard method.
Background technique
Nuclear reactor is typically provided with tens of for measuring the in-pile instrument of reactor core neutron fluence rate, in reactor operation
Period, these in-pile instruments pass through pressure vessel and upper-part in-reactor component, are inserted into fuel assembly, and in reactor shutdown, pressure is held
Device is uncapped reload before, need to detach these in-pile instruments fuel assembly, and be the one section high irradiation in insertion fuel assembly
The in-pile instrument of dosage provides shielding and protection, and there are two types of currently used solutions: one is by in-pile instrument by root from
Lift in fuel assembly to upper-part in-reactor component, embrittlement after this method is irradiated due to in-pile instrument is easy to be stuck in top heap
In inner member, and pull and push by root that in-pile instrument is larger to the irradiation dose of operator, and the operating time is longer；Second is that in upper bearing
The guide frame of a set of complexity is set above column, after pressure vessel is uncapped, first integrally lifts the guide frame, make in-pile instrument into
In the gauge pipe for entering upper support column and guide frame, this method needs the guide frame complicated in upper-part in-reactor component setting, meeting
The installation and maintenance of control rod guidance set are influenced, and after lifting device needed for this method should be able to lift guide frame, with upper
Portion's in-pile component is stored together, causes lifting device and operating procedure all very complicated.
Summary of the invention
It is during the refueling period the protection structure and its guard method for protecting in-pile instrument line the purpose of the present invention is designing,
Achieve the purpose that once to be promoted that operation can complete upper-part in-reactor component, in-pile instrument line is integrally promoted, and can not to reactor core
Instrument line, which does additional elevation operation, can protect in-pile instrument line, so that in-pile instrument line opposite upper parts in-pile component is not transported
It is dynamic, avoid in-pile instrument line from being difficult to be inserted into.
The present invention is achieved through the following technical solutions:
The protection structure of in-pile instrument line is protected, the upper support column including belonging to upper-part in-reactor component, further includes for protecting
The sleeve part of in-pile instrument line is protected, during nuclear reactor works, sleeve part is located in upper support column, and in-pile instrument line is located at casing
In part；It is characterized in that, in-pile instrument line is static relative to upper support column and with structure in the heap of top during nuclear reactor is safeguarded
Part, upper support column are integrally promoted, and described sleeve pipe part can pass through free movement below the upward support column in upper support column lower end and cover
The end of in-pile instrument line.
Design principle of the invention are as follows: in the prior art, there is a kind of technology to use internal and external casing structure, and internal and external casing
For structure setting in upper support column, technical principle is that the upper end of outer tube and the lower end of inner sleeve carry out limit processing, and interior
Casing is mounted in a component, when maintenance, first lifting assembly, so that inner sleeve is drawn upwardly out from upper support column, and later, inner sleeve
Pipe just drives outer tube to continue to rise so that outer tube is drawn upwardly out from upper support column, in lifting process, in-pile instrument line from
Extraction enters upper support column in fuel assembly.The design philosophy of the technical solution is to be lifted up in-pile instrument line, in-pile instrument
Line has more part and is just protected using the internal and external casing component that can be extracted out above upper support column in upper support column is arranged in.This
Kind of method has the following disadvantages: its is complicated for operation, and process is first lifting assembly, so that in-pile instrument line is from fuel assembly
Middle extraction is simultaneously protected using casing, then promotes upper-part in-reactor component again, is resetted complexity, is needed upper-part in-reactor component first
Installation is in place, and in-pile instrument line is then inserted into fuel assembly again, and since in-pile instrument line is flexible cord, down process easily exists
Bending in pipeline, therefore, in-pile instrument line are very easy to be inserted into after encountering deformation from the process moved in upper support column, make
It is very long at the duration is restored, and the program needs to carry out in-pile instrument line individually to promote operation, needs to pull in-pile instrument
Line increases the risk so that in-pile instrument thread breakage.In order to overcome the above problem, what the present invention innovated proposes a kind of design
Thought is ensuring that with the holding of upper support column relative motion does not occur for in-pile instrument line in lifting process, allows in-pile instrument line
It is promoted together with upper support column, upper-part in-reactor component, is based on the design scheme, then in lifting process, in-pile instrument line gesture
The part that must be extracted out, and extract out from fuel assembly will necessarily then be exposed to the lower section of upper-part in-reactor component, i.e., upper support column
Lower section, in order to protect the part, the sleeve design for proposing a kind of free-falling of the invention, i.e., in upper support column
Sleeve part is set, while can guarantee that sleeve part can pass through free movement below the upward support column in upper support column lower end and cover reactor core
The end of instrument line, in this way in lifting process, since upper support column rises, sleeve part then can go up relatively support column and fall, and
And be kept in contact between fuel assembly always under the action of self-weight, avoid the exposure of in-pile instrument line.Highest is arrived until being promoted
When position, in-pile instrument line is extracted out from fuel assembly completely at this time, and completely into being protected by it in sleeve part.We have found that
For in the threading operating process of long range, the part of the leading portion of line is not flexible in inserting process, and hindfoot portion, due to
The influence of leading portion weight is easily bent, and design scheme of the invention, opposite with upper support column due to not having when restoring
Movement, therefore, leading portion hindfoot portion is in upright state, and entirely upper support column, sleeve part are equivalent to a very long aid arm,
Therefore, the in-pile instrument line of front section, i.e., be easily inserted into fuel assembly close to the part of fuel assembly.
For the reactor of certain model, since the length of upper support column is enough or the length ratio of insertion in-pile instrument line
When shorter, therefore, when described sleeve pipe part is a casing, described sleeve pipe can be passed through below the upward support column in upper support column lower end certainly
By moving, and the upper end of casing is extended and can be captured by the constraint mouth of upper support column lower end.
For the reactor of certain model, since the length of upper support column is inadequate or the length ratio of insertion in-pile instrument line
When longer, described sleeve pipe part includes outer tube and the inner sleeve that is arranged in outer tube；The outer tube can pass through upper support column
Free movement below the upward support column in lower end, and the upper end of outer tube is extended and can be caught by the constraint mouth of upper support column lower end
It obtains；The inner sleeve can pass through free movement below the upward support column in lower end of outer tube, and the upper end of inner sleeve is extended simultaneously
It can be captured by the constraint mouth of upper support column lower end.The structure can meet the needs of protection length using 2 casings, equivalent,
The present invention can also be designed using 3 or the casing of four or more using aforesaid way.
Since what the present invention used protects the sleeve part of in-pile instrument line for the design of free-falling formula, inevitably due to obstruction
Phenomenon causes sleeve part to can not be successfully whereabouts, for this purpose, the invention proposes 2 kinds of solutions: the first is that design is sufficiently long
Spring so that spring can be kept in contact with sleeve part always completely in not pressured state, ensure that in this way sleeve part not by
The influence of choking phenomenon；Second is that use can move freely the spring in upper support column, and give both ends of the spring that counterweight is arranged
Component, such as the positioning ring and fulcrum bearing to be referred to behind us, spring, positioning ring and fulcrum bearing form an inertia component,
When encountering choking phenomenon causes sleeve part to can not be successfully whereabouts, we can shake entire upper-part in-reactor component, above-mentioned at this time
Inertia component will freely hit sleeve part in upper support column, unblock phenomenon with this.
Match the technical solution of the first above-mentioned solution choking phenomenon are as follows: be additionally provided with spiral bullet in the upper support column
Spring, the helical spring are located above sleeve part, and in-pile instrument line enters sleeve part after running through helical spring；Nuclear reactor work
Period, helical spring are compressed, provide a downward axial compression power for sleeve part；During nuclear reactor is safeguarded, spiral bullet
The axial compression power that spring is released, that one is provided for sleeve part is downward with overcome sleeve part move downward formed in friction
Power.
Match it is above-mentioned second solution choking phenomenon technical solution are as follows: be additionally provided in the upper support column positioning ring and
Fulcrum bearing, positioning ring are placed in right above helical spring, and helical spring is placed in right above fulcrum bearing, fulcrum bearing be placed in sleeve part just on
Side, the positioning ring and fulcrum bearing, helical spring can freely up and down slide in upper support column, and in-pile instrument line sequentially passes through
Positioning ring, helical spring, fulcrum bearing.
In order to solve the problem on deformation of helical spring, pogo barrel, above-mentioned spiral bullet are additionally provided in the upper support column
Spring is covered in pogo barrel outer wall, and in-pile instrument line enters sleeve part after running through pogo barrel, and pogo barrel can be with helical spring one
Play sliding.Pogo barrel plays guiding role.
Since helical spring is rapid wear product, under long duration of action, helical spring can fail, and replace spiral bullet for convenience
Spring, further includes the threaded sleeve being arranged in upper support column upper port, and threaded sleeve lower end is provided with positioning ring, in threaded sleeve
It is provided with pogo barrel, the upper end of pogo barrel is flared and can be captured by positioning ring, and pogo barrel lower end is provided with fulcrum bearing, institute
Spiral spring cover is stated in pogo barrel outer wall, between positioning ring and fulcrum bearing, in-pile instrument line sequentially passes through helical spring
Threaded sleeve, pogo barrel, fulcrum bearing.When needing with changing, we only need to remove threaded sleeve, due to threaded sleeve and spring
There are interaction relations for casing, and helical spring is limited between positioning ring and fulcrum bearing, therefore, only need to remove threaded sleeve just
Integrally helical spring, positioning ring and fulcrum bearing, pogo barrel can be taken out together, after replacement, then whole assembly, it operates non-
It is often simple.
The upper-part in-reactor component further includes support plate and reactor core upper plate, and upper support column is installed on support plate and reactor core upper plate
Between.
The guard method of protection structure based on the protection in-pile instrument line,
Including following procedure:
Lifting process: when in during nuclear reactor maintenance, upper-part in-reactor component need to only be promoted, in-pile instrument
Line is static relative to upper support column and is integrally promoted with upper-part in-reactor component, upper support column, upper-part in-reactor component and heap in-core
Fuel assembly separation；
Separation process: it is extracted out from fuel assembly the part in in-pile instrument line insertion fuel assembly；
Protection process: sleeve part free movement, sleeve part pass through free movement below the upward support column in upper support column lower end
And cover the end of in-pile instrument line.
It further include the protection that is hampered when being hindered in sleeve part free movement with upper support column or/and in-pile instrument line
Process,
Be hampered protection process: upper-part in-reactor component, upper support column is shaken up and down, so that positioning ring, helical spring, fulcrum bearing
Freely up and down concussion movement overcomes obstruction with inertial impaction sleeve part with this in upper support column.
Apparatus of the present invention advantage: the present invention provides one kind during reactor refuling, can be the reactor core in fuel assembly
Instrument provides the protection structure of protection and function of shielding, which is mounted in support column, before reactor refuling, lifts
When portion's in-pile component, sleeve part gradually stretches out downwards from upper support column (being reactor core upper plate below upper support column), for from reactor core
One section of in-pile instrument line of extraction provides shielding and protection, after reactor refuling, when being put into upper-part in-reactor component, and the set
Pipe fitting is supported in upper pipe seat of fuel component, and with being gradually put into for upper-part in-reactor component, which is gradually supported in retraction
In column, until upper-part in-reactor component is installed, at this point, again heavy by internal and external casing component protection and one section of in-pile instrument of shielding
Newly enter in fuel assembly.The multiple sheath assembly does not influence the structure arrangement and mounting means of upper-part in-reactor component, does not need
Individual hoisting tool special is able to achieve during reactor refuling, is the reactor core of one section of high irradiation dose in fuel assembly
Instrument provides protection and shielding.It does not need to take out sleeve part, so that it may take out spring at the top of upper support column, facilitate to irradiation
The helical spring of performance decline is replaced afterwards.Use internal and external casing component during the refueling period for one section of reactor core in fuel assembly
Instrument provides protection and shielding and is applied in foreign countries, but in external scheme, has been all made of the branch in upper-part in-reactor component
One piece of grid orifice plate is set above board, internal and external casing component is fixed on to the bottom of grid orifice plate, during the refueling period, is first used
Grid orifice plate is promoted certain height relative to upper-part in-reactor component by dedicated operational instrument, wears internal and external casing component upwards
Upper support column out, while in-pile instrument line is promoted, which will affect the installation and maintenance replacement of control rod guidance set,
And the program needs grid orifice plate and internal and external casing component promoting certain height, required operation relative to upper-part in-reactor component
Tool and operating procedure are more complex.The movement of in-pile instrument line will cause in-pile instrument line and be difficult to the difficulty restored, reinserted
It is significantly greatly increased, greatly delays the time that reactor work is restored.
Sleeve part of the present invention lifts with upper-part in-reactor component, and gradually stretches out below reactor core upper plate, does not need to make
With special operating tool, operating process is simple, does not also need that grid orifice plate is arranged in upper-part in-reactor component, simplifies top heap
Inner member facilitates the installation and maintenance replacement of control rod guidance set.The internal and external casing element end is supported on fuel assembly
In tube socket, the cooperation of upper-part in-reactor component and fuel assembly, and the buffer spring limit assembly of the multiple cannula structure are not influenced
Higher than internal and external casing component, taking-up helical spring can be facilitated to be replaced.
Detailed description of the invention
Attached drawing described herein is used to provide to further understand the embodiment of the present invention, constitutes one of the application
Point, do not constitute the restriction to the embodiment of the present invention.In the accompanying drawings:
Fig. 1 is the schematic view of the mounting position during nuclear reactor operation；
Fig. 2 is the enlarged view I of Fig. 1；
Fig. 3 is the structural schematic diagram of inner sleeve insertion outer tube；
Fig. 4 is the structural schematic diagram that inner sleeve is extracted out from outer tube；
Fig. 5 is structural schematic diagram when helical spring is compressed；
Fig. 6 is structural schematic diagram when helical spring is released；
Fig. 7 is the enlarged view II of Fig. 2；
Fig. 8 is the enlarged view III of Fig. 2；
Fig. 9 is the schematic view of the mounting position before nuclear reactor reloads；
Figure 10 is the enlarged view IV of Fig. 9；
In figure: 1-multiple cannula structure；2-upper-part in-reactor components；3-upper support columns；4-hanging basket components；5-fuel
Component；6-reactor core upper plates；7-guide pipes；8-guide posts；9-support plates；10-internal and external casing components；11-buffer springs
Limit assembly；12-inner sleeves；13-stop collars；14-outer tubes；15-closed-loops；16-threaded sleeves；17-positioning rings；
18-pogo barrels；19-fulcrum bearings；20-helical springs；21-mechanical splices；22-in-pile instrument lines；23-fuel assemblies
Upper tube socket.
Specific embodiment
To make the objectives, technical solutions, and advantages of the present invention clearer, below with reference to embodiment and attached drawing, to this
Invention is described in further detail, and exemplary embodiment of the invention and its explanation for explaining only the invention, are not made
For limitation of the invention.
Embodiment 1
As shown in Figures 1 to 10, the protection structure of in-pile instrument line, the upper branch including belonging to upper-part in-reactor component 1 are protected
Bearing column 3 further includes the sleeve part for protecting in-pile instrument line 22, and during nuclear reactor works, sleeve part is located at upper support column 3
Interior, in-pile instrument line 22 is located in sleeve part；It is characterized in that, in-pile instrument line 22 is relative to upper during nuclear reactor is safeguarded
Support column 3 is static and with upper-part in-reactor component 1, the whole promotion of upper support column 3, and described sleeve pipe part can pass through upper 3 lower end of support column
Upward 3 lower section free movement of support column and the end for covering in-pile instrument line 22.
Design principle of the invention are as follows: in the prior art, there is a kind of technology to use internal and external casing structure, and internal and external casing
For structure setting in upper support column 3, technical principle is that the upper end of outer tube and the lower end of inner sleeve carry out limit processing, and interior
Casing is mounted in a component, when maintenance, first lifting assembly, so that inner sleeve is drawn upwardly out from upper support column 3, it is later, interior
Casing just drives outer tube to continue to rise, so that outer tube is drawn upwardly out from upper support column 3, in lifting process, in-pile instrument
Line 22 is extracted out from fuel assembly into upper support column 3.The design philosophy of the technical solution is to be lifted up in-pile instrument line 22,
In-pile instrument line 22 has more part just using the internal and external casing group that can be extracted out above upper support column 3 in upper support column 3 is arranged in
Part is protected.This method has the following disadvantages: its is complicated for operation, and process is first lifting assembly, so that reactor core instrument
Table line 22 is extracted out from fuel assembly and is protected using casing, then promotes upper-part in-reactor component 1 again, resets complexity, is needed
First upper-part in-reactor component 1 to be installed in place, in-pile instrument line 22 is then inserted into fuel assembly again, due to in-pile instrument line
22 be flexible cord, and down process is easily bent in pipeline, and therefore, the process that in-pile instrument line 22 is moved from upper support column 3 is non-
It cannot be inserted into after being often likely to encounter deformation, it is very long cause the recovery duration, and the program needs to carry out list to in-pile instrument line 22
Only promotion operation, needs to pull in-pile instrument line 22, increases so that the risk that in-pile instrument line 22 is broken.On overcoming
State problem, what the present invention innovated proposes a kind of design philosophy, be ensuring that in-pile instrument line 22 in lifting process with upper branch
Relative motion does not occur for the holding of bearing column 3, allows in-pile instrument line 22 to be promoted together with upper support column 3, upper-part in-reactor component 1, is based on
The design scheme, then in-pile instrument line 22 will certainly be extracted out from fuel assembly in lifting process, and the part extracted out is then
The lower section of upper-part in-reactor component 1, i.e., the lower section of upper support column 3, in order to protect the part, the invention will necessarily be exposed to
The sleeve design for proposing a kind of free-falling, i.e., sleeve part is set in upper support column 3, while can guarantee that sleeve part can pass through
The upward 3 lower section free movement of support column in upper 3 lower end of support column and the end for covering in-pile instrument line 22, in this way in lifting process
In, since upper support column 3 rises, sleeve part then can relatively upper support column 3 fall, and under the action of self-weight always with fuel
It is kept in contact between component, avoids the exposure of in-pile instrument line 22.When arriving extreme higher position until being promoted, in-pile instrument line 22 is complete at this time
It is extracted out entirely from fuel assembly, and completely into being protected by it in sleeve part.We have found that the threading for long range operated
Cheng Zhong, the part of the leading portion of line should not be bent in inserting process, and hindfoot portion, since the influence of leading portion weight is easily curved
Song, and design scheme of the invention, when restoring, since relative motion does not occur with upper support column 3, leading portion back segment
It is partially in upright state, entirely upper support column 3, sleeve part are equivalent to a very long aid arm, therefore, the heap of front section
Core instrument line 22, i.e., be easily inserted into fuel assembly close to the part of fuel assembly.
Embodiment 2
On that basi of the above embodiments, for the reactor of certain model, since the length of upper support column 3 is enough or slotting
Enter in-pile instrument line 22 length it is shorter when, therefore, described sleeve pipe part be a casing when, described sleeve pipe can pass through upper bearing
The upward 3 lower section free movement of support column in 3 lower end of column, and the upper end of casing is extended and can be by the constraint mouth of upper 3 lower end of support column
Capture.A structure when casing is not provided in figure.
Embodiment 3
On that basi of the above embodiments, for the reactor of certain model, since the length of upper support column 3 is inadequate or slotting
Enter in-pile instrument line 22 length it is long when, described sleeve pipe part includes outer tube 14 and the inner sleeve that is arranged in outer tube 14
12；The outer tube 14 can pass through the upward 3 lower section free movement of support column in upper 3 lower end of support column, and the upper end quilt of outer tube 14
Expand and can be captured by the constraint mouth of upper 3 lower end of support column；The lower end that the inner sleeve 12 can pass through outer tube 14 supports upwards
3 lower section free movement of column, and the upper end of inner sleeve 12 is extended and can be captured by the constraint mouth of upper 3 lower end of support column.The structure
Can meet the needs of protection length using 2 casings, equivalent, the present invention can also be using 3 or the set of four or more
Pipe, is designed using aforesaid way.Structure when 2 casings is provided in figure.The outer tube 14, inner sleeve 12 constitute multiple casing
Structure 1, certainly, the multiple cannula structure 1 can also mutually be socket-connected composition using more casings.
Embodiment 4
On that basi of the above embodiments, the sleeve part of the protection in-pile instrument line 22 used due to the present invention is free-falling
The design of formula, inevitably since choking phenomenon causes sleeve part to can not be successfully whereabouts, for this purpose, the invention proposes 2 kinds of solutions:
The first is the sufficiently long spring of design, so that spring can be kept in contact with sleeve part, so always completely in not pressured state
Ensure that sleeve part is not blocked the influence of phenomenon；Second is that use can move freely the spring in upper support column 3,
And weight member, such as the positioning ring 17 and fulcrum bearing 19 to be referred to behind us, spring, positioning ring 17 are set to both ends of the spring
An inertia component is formed with fulcrum bearing 19, when encountering choking phenomenon causes sleeve part to can not be successfully whereabouts, we can be trembled
Entire upper-part in-reactor component 1 is moved, above-mentioned inertia component will freely hit sleeve part in upper support column 3 at this time, release with this
Choking phenomenon.
Match the technical solution of the first above-mentioned solution choking phenomenon are as follows: be additionally provided with spiral bullet in the upper support column 3
Spring 20, the helical spring 20 are located above sleeve part, and in-pile instrument line 22 enters sleeve part after running through helical spring 20；Core is anti-
During answering heap to work, helical spring 20 is compressed, provides a downward axial compression power for sleeve part；Nuclear reactor maintenance phase
Between, helical spring 20 is released, provides a downward axial compression power for sleeve part to overcome sleeve part to move downward middle institute
The frictional force of formation.
Match the technical solution of above-mentioned second of solution choking phenomenon are as follows: be additionally provided with positioning ring in the upper support column 3
17 and fulcrum bearing 19, positioning ring 17 is placed in right above helical spring 20, and helical spring 20 is placed in right above fulcrum bearing 19, fulcrum bearing
19 are placed in right above sleeve part, and the positioning ring 17 and fulcrum bearing 19, helical spring 20 can be in upper support columns 3 freely up and down
Sliding, in-pile instrument line 22 sequentially pass through positioning ring 17, helical spring 20, fulcrum bearing 19.
On the basis of the above embodiments, it in order to solve the problem on deformation of helical spring 20, is also set in the upper support column 3
Be equipped with pogo barrel 18,20 sets of above-mentioned helical spring in 18 outer wall of pogo barrel, after in-pile instrument line 22 runs through pogo barrel 18
Sleeve pipe part, pogo barrel 18 can be slided with helical spring 20.Pogo barrel 18 plays guiding role.
Embodiment 5
On that basi of the above embodiments, since helical spring 20 is rapid wear product, under long duration of action, helical spring 20
It can fail, replace helical spring 20 for convenience, further include the threaded sleeve 16 being arranged in upper 3 upper port of support column, screw thread
16 lower end of casing is provided with positioning ring 17, pogo barrel 18 is provided in threaded sleeve 16, the upper end flaring of pogo barrel 18 is simultaneously
It can be captured by positioning ring 17,18 lower end of pogo barrel is provided with fulcrum bearing 19, and 20 sets of the helical spring is outside pogo barrel 18
Wall, for helical spring 20 between positioning ring 17 and fulcrum bearing 19, in-pile instrument line 22 sequentially passes through threaded sleeve 16, spring pocket
Pipe 18, fulcrum bearing 19.When needing with changing, we only need to remove threaded sleeve 16, due to threaded sleeve 16 and pogo barrel 18
There are interaction relations, and helical spring 20 is limited between positioning ring 17 and fulcrum bearing 19, therefore, need to only remove threaded sleeve
16 will integrally take out helical spring 20, positioning ring 17 and fulcrum bearing 19, pogo barrel 18 together, after replacement, then whole dress
Match, operates very simple.
On that basi of the above embodiments, the upper-part in-reactor component 1 further includes support plate 9 and reactor core upper plate 6, upper support column
It is installed between support plate 9 and reactor core upper plate 6.
Fuel assembly 5 is arranged in hanging basket component 4 in the figure, and support plate 9, reactor core upper plate 6, upper support column 3 are one whole
Body structure, interior guide pipe 7 is in-pile instrument line 22, and guide pipe 7 is mounted on threaded sleeve using mechanical splice 21, outer tube
Lower end expands mouth using the upper end of closed-loop capture inner sleeve.
Embodiment 6
On that basi of the above embodiments, the guard method of the protection structure based on the protection in-pile instrument line,
Including following procedure:
Lifting process: when in during nuclear reactor maintenance, upper-part in-reactor component 1 need to only be promoted, reactor core instrument
Table line 22 it is static relative to upper support column 3 and with upper-part in-reactor component 1, upper support column 3 is whole is promoted, upper-part in-reactor component 1 with
The fuel assembly 5 of heap in-core separates；
Separation process: it is extracted out from fuel assembly 5 part that in-pile instrument line 22 is inserted into fuel assembly 5；
Protection process: sleeve part free movement, sleeve part pass through upward 3 lower section of support column in upper 3 lower end of support column and freely transport
Move and cover the end of in-pile instrument line 22.
Embodiment 7
On that basi of the above embodiments, when occurring in sleeve part free movement with upper support column 3 or/and in-pile instrument line 22
It further include the protection process that is hampered when obstruction,
Be hampered protection process: up and down concussion upper-part in-reactor component 1, upper support column 3 so that positioning ring 17, helical spring 20,
The freely up and down concussion movement in upper support column 3 of fulcrum bearing 19 overcomes obstruction with inertial impaction sleeve part with this.
When specific to above-mentioned implementation, part is that the decomposition of each figure illustrates below:
As shown in Figure 1, multiple cannula structure 1 is located in the upper bearing of upper-part in-reactor component 2 during nuclear reactor is run
In column 3, upper-part in-reactor component 2 has been placed in hanging basket component 4 at this time, and fuel assembly 5 is mounted on the reactor core of upper-part in-reactor component 2
Between plate 6 and hanging basket component 4, upper 3 top of support column is connected with guide pipe 7, and the other end of guide pipe 7 is fixed in guide post 8,
Guide post 8 is mounted on the support plate 9 of upper-part in-reactor component 2.
It is the enlarged view I of Fig. 1 shown in Fig. 2, is mounted in support column 3 and sets internal and external casing component 10 and buffer spring limit
Hyte part 11, buffer spring limit assembly 11 are mounted on 10 top of internal and external casing component.
Internal and external casing component 10 is as shown in figure 3, by stop collar 13, the outer tube 14 and outer on inner sleeve 12, inner sleeve 12
The suit of closed-loop 15 of 14 lower end of casing is welded, and inner sleeve 12 can slide up and down in outer tube 14, as shown in figure 3,
When 12 upward sliding of inner sleeve to the top of outer tube 14, stop collar 13 withstands in closed-loop 15 and carries out axial limit to inner sleeve 12
Position；As shown in figure 4, being supported in closed-loop 15 when inner sleeve 12 slides down to 14 bottom end of outer tube and carrying out axial limiting.
Buffer spring limit assembly 11 is as shown in figure 5, by threaded sleeve 16, positioning ring 17, pogo barrel 18, fulcrum bearing 19
It is formed with 20 assembly welding of helical spring, pogo barrel 18 can slide up and down in threaded sleeve 16, as shown in figure 5, screw thread
When 16 upward sliding of casing, compression helical spring 20 provides pressing force, when 16 slide downward of threaded sleeve, as shown in fig. 6, bearing
Axial limiting is carried out on positioning ring 17.The figure is only a kind of mode that spring is arranged, other embodiments in above-described embodiment
Similar structures can be used, other than the length of spring or manner, structure is roughly the same.
Fig. 7 show the enlarged view II of Fig. 2, and Fig. 8 show the enlarged view III of Fig. 2, and Fig. 7 and Fig. 8 show top
In-pile component 2 be put into hanging basket component 4 and it is in place after, multiple cannula structure 1 state in place in upper support column 3.Such as Fig. 7 and figure
Shown in 8, threaded sleeve 16 is to be threadedly engaged with upper support column 3, and 16 top of threaded sleeve passes through on mechanical splice 21 and support plate 9
The guide pipe 7 of side connects, and the end of inner sleeve 12 is withstood in upper pipe seat of fuel component 23, and stop collar 13 withstands on closing upwards at this time
On ring 15, the top of outer tube 14 is pushed to withstand in fulcrum bearing 19, and compress the spiral bullet between fulcrum bearing 19 and positioning ring 17
Spring 20, compressed helical spring 20 provide pretightning force, and inner sleeve 12 and outer tube 14 are compressed and limited in fulcrum bearing 19 and upper
Between tube socket 23.In-pile instrument 22 is after the insertion of guide pipe 7, threadingly casing 16, pogo barrel 18, outer tube 14 and inner sleeve
12 through-hole is inserted directly into upper pipe seat of fuel component 23.
Before reactor uncaps and reloads, as shown in figure 9, when slinging upper-part in-reactor component 2 out of hanging basket component 4, it is interior
Casing 12 and outer tube 14 extend downwardly reactor core upper plate 6 out of upper support column 3, and Figure 10 is the enlarged view IV of Fig. 9, work as outer tube
When 14 top is supported on 3 bottom end of support column, the continuation of inner sleeve 12 is stretched out out of outer tube 14, until the top of inner sleeve 12
It is supported in closed-loop 15, closes outer tube 14 from the inner sleeve 12 that reactor core upper plate 6 extends downwardly and extracted out out of fuel assembly 5
The in-pile instrument 22 of one section high irradiation provides shielding and protection.
When reactor refuling terminates, and upper-part in-reactor component 2 is put into hanging basket component 4, as shown in figure 8, inner sleeve 12
End is inserted into upper pipe seat of fuel component 23, due to the axial limiting of upper pipe seat of fuel component 23, with upper-part in-reactor component 2 by
Gradually downwards, as shown in Fig. 3 left figure, inner sleeve 12 is moved upward to stop collar 13 along outer tube 14 relative to upper-part in-reactor component 2
It is contacted with closed-loop 15, as shown in fig. 7, inner sleeve 12 drives outer tube 14 to be moved upward to and support along upper support column 3 at this time
Seat 19 contacts, and pushes the upward compression helical spring 20 of fulcrum bearing 19, until on reactor core upper plate shown in FIG. 16 and fuel assembly
Tube socket 23 is bonded, and compressed helical spring 20 provides pretightning force, and inner sleeve 12 and outer tube 14 are compressed limit in fulcrum bearing
Between 19 and upper pipe seat of fuel component 23, during inner sleeve 12 and outer tube 14 are moved upwards relative to reactor core upper plate 6, by
Inner sleeve 12 and one section of in-pile instrument 22 of the protection of outer tube 14 and shielding enter in fuel assembly 5 again.
Above-described specific embodiment has carried out further the purpose of the present invention, technical scheme and beneficial effects
It is described in detail, it should be understood that being not intended to limit the present invention the foregoing is merely a specific embodiment of the invention
Protection scope, all within the spirits and principles of the present invention, any modification, equivalent substitution, improvement and etc. done should all include
Within protection scope of the present invention.
Claims (10)
1. protecting the protection structure of in-pile instrument line, the upper support column (3) including belonging to upper-part in-reactor component (1) further includes using
In the sleeve part of protection in-pile instrument line (22), during nuclear reactor works, sleeve part is located in upper support column (3), reactor core instrument
Table line (22) is located in sleeve part；It is characterized in that, in-pile instrument line (22) is relative to upper support column during nuclear reactor is safeguarded
(3) static and with upper-part in-reactor component (1), upper support column (3) integrally promoted, described sleeve pipe part can pass through upper support column (3) under
It holds upward support column (3) lower section free movement and covers the end of in-pile instrument line (22).
2. the protection structure of protection in-pile instrument line according to claim 1, which is characterized in that described sleeve pipe part is one
When casing, described sleeve pipe can pass through free movement below the upward support column in upper support column (3) lower end (3), and the upper end quilt of casing
Expand and can be captured by the constraint mouth of upper support column (3) lower end.
3. the protection structure of protection in-pile instrument line according to claim 1, which is characterized in that described sleeve pipe part includes outer
Casing (14) and the inner sleeve (12) being arranged in outer tube (14)；The outer tube (14) can pass through upper support column (3) lower end
Free movement below upward support column (3), and the upper end of outer tube (14) is extended and can be by the constraint of upper support column (3) lower end
Mouth capture；The inner sleeve (12) can pass through free movement below the upward support column in lower end (3) of outer tube (14), and inner sleeve
(12) upper end is extended and can be captured by the constraint mouth of upper support column (3) lower end.
4. the protection structure of protection in-pile instrument line according to claim 1 or 2 or 3, which is characterized in that the upper bearing
It is additionally provided with helical spring (20) in column (3), the helical spring (20) is located above sleeve part, and in-pile instrument line (22) runs through
Helical spring (20) enters sleeve part afterwards；During nuclear reactor works, helical spring (20) is compressed, provides one for sleeve part
Downward axial compression power；During nuclear reactor is safeguarded, helical spring (20) is released, provides a downward axis for sleeve part
To extruding force with overcome sleeve part move downward formed in frictional force.
5. the protection structure of protection in-pile instrument line according to claim 4, which is characterized in that the upper support column (3)
It is inside additionally provided with positioning ring (17) and fulcrum bearing (19), positioning ring (17) is placed in right above helical spring (20), helical spring
(20) it is placed in right above fulcrum bearing (19), fulcrum bearing (19) is placed in right above sleeve part, the positioning ring (17) and fulcrum bearing
(19), helical spring (20) can freely up and down slide in upper support column (3), and in-pile instrument line (22) sequentially passes through positioning ring
(17), helical spring (20), fulcrum bearing (19).
6. the protection structure of protection in-pile instrument line according to claim 4, which is characterized in that the upper support column (3)
It is inside additionally provided with pogo barrel (18), above-mentioned helical spring (20) covers in pogo barrel (18) outer wall, and in-pile instrument line (22) passes through
It wears pogo barrel (18) and enters sleeve part afterwards, pogo barrel (18) can be slided with helical spring (20).
7. the protection structure of protection in-pile instrument line according to claim 4, which is characterized in that further include being arranged in upper branch
Threaded sleeve (16) in bearing column (3) upper port, threaded sleeve (16) lower end are provided with positioning ring (17), in threaded sleeve (16)
It is provided with pogo barrel (18), the upper end of pogo barrel (18) is flared and can be captured by positioning ring (17), under pogo barrel (18)
End is provided with fulcrum bearing (19), and the helical spring (20) covers in pogo barrel (18) outer wall, and helical spring (20) is located at positioning
Between ring (17) and fulcrum bearing (19), in-pile instrument line (22) sequentially passes through threaded sleeve (16), pogo barrel (18), fulcrum bearing
(19).
8. the protection structure of protection in-pile instrument line according to claim 1 or 2 or 3, which is characterized in that the top heap
Inner member (1) further includes support plate (9) and reactor core upper plate (6), upper support column be installed on support plate (9) and reactor core upper plate (6) it
Between.
9. special based on the guard method for the protection structure for protecting in-pile instrument line described in any one of claim 1-8
Sign is,
Including following procedure:
Lifting process: when in during nuclear reactor maintenance, upper-part in-reactor component (1) need to only be promoted, in-pile instrument
Line (22) is static relative to upper support column (3) and is integrally promoted with upper-part in-reactor component (1), upper support column (3), structure in the heap of top
Part (1) is separated with the fuel assembly (5) of heap in-core；
Separation process: in-pile instrument line (22) is inserted into the extraction from fuel assembly (5) of the part in fuel assembly (5)；
Protection process: sleeve part free movement, sleeve part passes through freely to be transported below the upward support column in upper support column (3) lower end (3)
Move and cover the end of in-pile instrument line (22).
10. guard method according to claim 9, which is characterized in that when in sleeve part free movement with upper support column (3)
Or/and in-pile instrument line (22) is when hindering, and further includes the protection process that is hampered,
Be hampered protection process: upper-part in-reactor component (1), upper support column (3) is shaken up and down, so that positioning ring (17), helical spring
(20), fulcrum bearing (19) freely up and down concussion movement in upper support column (3) overcomes obstruction with inertial impaction sleeve part with this.
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| Application Number | Priority Date | Filing Date | Title |
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| CN201710321599.2A CN107093471B (en) | 2017-05-09 | 2017-05-09 | Protect the protection structure and its guard method of in-pile instrument line |
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| CN201710321599.2A CN107093471B (en) | 2017-05-09 | 2017-05-09 | Protect the protection structure and its guard method of in-pile instrument line |
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| CN107093471B true CN107093471B (en) | 2019-01-08 |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| RU2726737C1 (en) * | 2019-12-03 | 2020-07-15 | Акционерное Общество "Российский Концерн По Производству Электрической И Тепловой Энергии На Атомных Станциях" (Ао "Концерн Росэнергоатом") | External heat insulation of nuclear reactor housing and system for installation of external heat insulation of housing of nuclear reactor |
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| US9478320B2 (en) * | 2014-08-18 | 2016-10-25 | Westinghouse Electric Company Llc | Method for in-core instrumentation withdrawal from the core of a pressurized water reactor |
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| RU2726737C1 (en) * | 2019-12-03 | 2020-07-15 | Акционерное Общество "Российский Концерн По Производству Электрической И Тепловой Энергии На Атомных Станциях" (Ао "Концерн Росэнергоатом") | External heat insulation of nuclear reactor housing and system for installation of external heat insulation of housing of nuclear reactor |
| WO2021112714A1 (en) * | 2019-12-03 | 2021-06-10 | Акционерное Общество "Российский Концерн По Производству Электрической И Тепловой Энергии На Атомных Станциях" | External thermal insulation for a nuclear reactor vessel and system for installing same |
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| Publication number | Publication date |
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| CN107093471A (en) | 2017-08-25 |
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