CN106051722B - Nuclear power station steam generator lower horizontal supporting structure - Google Patents
Nuclear power station steam generator lower horizontal supporting structure Download PDFInfo
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- CN106051722B CN106051722B CN201610417349.4A CN201610417349A CN106051722B CN 106051722 B CN106051722 B CN 106051722B CN 201610417349 A CN201610417349 A CN 201610417349A CN 106051722 B CN106051722 B CN 106051722B
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- pedestal
- steam generator
- adjustment
- big end
- lower horizontal
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Classifications
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B37/00—Component parts or details of steam boilers
- F22B37/002—Component parts or details of steam boilers specially adapted for nuclear steam generators, e.g. maintenance, repairing or inspecting equipment not otherwise provided for
Abstract
The invention discloses a kind of nuclear power station steam generator lower horizontal supporting structures, it includes limiting the supporting arrangement that steam generator generates instantaneous displacement, supporting arrangement includes pedestal and the axial interval regulator being located on pedestal, the pedestal shape is ladder shaft-like, the outer diameter of pedestal gradually successively decreases and forms pedestal big end and pedestal time big end from back to front, the leading portion of pedestal big end is hollow structure, and pedestal big end leading portion internal diameter is bigger than pedestal time big end outer diameter, so that forming semidiameter Δ r between pedestal big end leading portion inner wall and pedestal time big end outer wall.Compared with prior art, the present invention has the following effects:1) simple using the base construction with pooling feature, cushion performance is excellent, installation, easy to maintain, effective reduction manufacture and installation cost;2) clearance measurement simple operation, and measuring result error is smaller;3) gap adjustment is more convenient, and this structure is effectively shortened the time of clearance measurement and adjustment, saves time cost and human cost.
Description
Technical field
The present invention relates to a kind of nuclear power station steam generator lower horizontal supporting structures.
Background technology
In normal conditions, nuclear power station steam generator supporting structure can provide supporting for steam generator, bear phase
Answer the bearing load under operating mode;Under reactor coolant loop normal operation, primary Ioops main system thermal expansion operating mode, steam hair
Raw device supporting structure can ensure that steam generator realizes free free thermal expansion and thermal walking;In earthquake or dehydration thing
Therefore when occurring (loss of-coolant accident (LOCA) hereinafter referred to as LOCA accident), steam generator supporting structure can limit the wink of steam generator
Between displacement, ensure the stability and security of reactor coolant loop, steam generator and civil engineering structure.
Published nuclear power station steam generator lower horizontal supporting structure is by 1 group of lateral Displacement seat 2 and front end limit base
Into concrete arrangement is as shown in Figure 1.Wherein, the supporting leg of lateral Displacement seat 2 has supporting leg I, II, III and IV 4 kind of specification;Front end
The supporting leg of limit base 1 has III two kinds of specifications of supporting leg II and supporting leg.As shown in Figure 2, limit base includes water to the concrete structure of limit base
Calm down position support supporting leg 3 and be fixed on steam generator by the cushion block 7 of supporting leg Horizontal limiting, supporting leg front end from it is rear to
Preceding buffer stopper 4, filler strip 5 and the adjustment block 6 for being equipped with adjacent fitting successively, adjustment block 6 and cushion block 7 with respect to and stay between the two
There is adjustment gap.Either lateral Displacement seat or front end limit base, they are all filled using a certain number of buffer stoppers 4 as buffering
It puts, to bear when earthquake or LOCA accident occur steam generator because the shock loading generated during instantaneous displacement to each limit base,
So as to ensure reactor coolant loop, steam generator and the stability and security of civil engineering structure.The front end face of each limit base with
Gap adjustment between corresponding cushion block mating surface is then realized by filler strip 5 and adjustment block 6, by adjusting the thickness of adjustment block 6
The gap width between 7 mating surface of adjustment block 6 and each cushion block is adjusted, to meet because drawing during reactor coolant loop temperature change
The free thermal walking of steam generator risen, while the instantaneous displacement of steam generator can be limited.
From above-mentioned nuclear power station steam generator lower horizontal supporting structure introduction, sent out in published nuclear power station steam
In raw device lower horizontal supporting structure, each limit base all employs the square buffer stopper of standard as buffer unit, and each /V
There are certain adjustment gap between the adjustment block and cushion block of seat, these adjustment gaps need to reload hot shutdown in each overhaul
It is measured under operating mode, afterwards according to the thickness for the gap examination value processing adjustment block being calculated, to ensure that adjustment gap exists
In acceptable scope.But there are following defects for this supporting structure:
1st, used square buffer stopper procurement cycle is longer, of high cost, and later stage installation, operation and maintenance are cumbersome;
2nd, gap measurement and adjustment every time reload when be required for repetitive operation, add manpower, the object of maintenance personal
The input of power;
3rd, since the adjustment gap between adjustment block and cushion block is smaller, measurement operating space is limited, and adjustment block is relatively
Long, measuring apparatus is difficult the adjustment gap accurately measured at these positions, causes measurement error larger;
4th, the adjustment gap width measured under hot shutdown operating mode of reloading every time is required for transferring to the company of specialty or mechanism to carry out
Gap evaluation, assessment is costly, and the duration is longer;
5th, scene needs the thickness for the result processing adjustment block evaluated according to gap, to ensure that adjustment gap width is tested in gap
In the range of receipts, the processes such as adjustment block processing, installation and adjustment are added.
The content of the invention
It is an object of the invention to:There is provided a kind of clearance measurement simple operation, gap nuclear power station steam hair easy to adjust
Raw device lower horizontal supporting structure.
In order to realize foregoing invention purpose, the present invention provides a kind of supportings of nuclear power station steam generator lower horizontal to tie
Structure, the supporting arrangement of instantaneous displacement is generated including limitation steam generator, and supporting arrangement includes pedestal and is located on pedestal
Axial interval regulator, the pedestal shape is ladder shaft-like, and the outer diameter of pedestal gradually successively decreases and form base from back to front
Seat big end and pedestal time big end, the leading portion of pedestal big end is hollow structure, and outside pedestal big end leading portion internal diameter big end more secondary than pedestal
Footpath is big, so that forming semidiameter Δ r between pedestal big end leading portion inner wall and pedestal time big end outer wall.
As a kind of improvement of nuclear power station steam generator lower horizontal supporting structure of the present invention, the axial gap adjustment
Device includes adjustment bolt, the adjustment bolt locking mechanism being located on pedestal and the adjustment threaded hole for being opened in pedestal front end face,
Adjustment bolt is screwed in adjustment threaded hole, is threaded in or out adjustment threaded hole by adjusting bolt to realize the tune of axial gap
Whole, adjustment bolt locking mechanism can make adjustment bolt fixation that can not rotate.
As a kind of improvement of nuclear power station steam generator lower horizontal supporting structure of the present invention, the adjustment bolt locking
Structure is included in the radial indentation being provided on the adjustment threaded hole hole wall of pedestal front end and clamping screw, and radial indentation will
The adjustment threaded hole hole wall of adjacent both sides separates and the radical length of radial indentation is at least bigger than pore wall thickness, positioned at radially
Axially extending bore is provided on adjustment threaded hole hole wall on front side of notch, is provided on the adjustment threaded hole hole wall on rear side of radial indentation
The coaxial locking screw pit with axially extending bore, clamping screw initially pass through axially extending bore and are screwed into locking screw pit, locking screw
Being threadedly coupled power and can oppress adjustment threaded hole hole wall on front side of radial indentation and tilt between bolt and locking screw pit, adjusts
Whole threaded hole hole wall inclination causes adjustment bolt is stuck can not rotate.
As a kind of improvement of nuclear power station steam generator lower horizontal supporting structure of the present invention, the radial indentation is located at
Close to the one side of pedestal front end face, the axial length of the adjustment threaded hole hole wall on front side of radial indentation is shorter for pedestal front end,
Adjust the easier inclination of threaded hole hole wall.
As a kind of improvement of nuclear power station steam generator lower horizontal supporting structure of the present invention, the footpath of the radial indentation
Bigger than pedestal front end outer radius, smaller than pedestal front end overall diameter to length, the radical length of radial indentation is than outside pedestal front end half
Footpath can so that greatly adjusting threaded hole hole wall is easier to tilt under the action of clamping screw.
As a kind of improvement of nuclear power station steam generator lower horizontal supporting structure of the present invention, the locking screw pit position
In on the radial symmetric line of radial indentation so that the radial direction arm of force of clamping screw is maximum, and adjustment threaded hole hole wall is in clamping screw
Under the action of be easier tilt.
As a kind of improvement of this practicality nuclear power station steam generator lower horizontal supporting structure, the pedestal big end is whole
For hollow structure, be so conducive to the manufacture processing of pedestal.
As a kind of improvement of nuclear power station steam generator lower horizontal supporting structure of the present invention, the pedestal big end is equipped with
Pedestal is fixed on concrete structure by mounting flange with facilitating.
As a kind of improvement of nuclear power station steam generator lower horizontal supporting structure of the present invention, further include and be respectively arranged on steaming
Lateral blocked frame, the preceding divider on steam generator main pipe hot leg center line of vapour generator main pipe hot leg center line both sides
And lateral-supporting platform and forward direction supporting platform on steam generator low head, lateral blocked frame and lateral-supporting platform one
One corresponds to, and preceding divider is corresponding with forward direction supporting platform, and each lateral blocked frame and preceding divider all include at least two supporting arrangements.
As a kind of improvement of nuclear power station steam generator lower horizontal supporting structure of the present invention, the lateral blocked frame includes two
A supporting arrangement, the preceding divider include three supporting arrangements.
Compared with prior art, nuclear power station steam generator lower horizontal supporting structure of the present invention has the following effects that:
1) simple using the base construction with pooling feature, cushion performance is excellent, installation, easy to maintain, effectively reduction
Manufacture and installation cost;
2) clearance measurement simple operation, and measuring result error is smaller;
3) gap adjustment is more convenient, and this structure is effectively shortened the time of clearance measurement and adjustment, when saving
Between cost and human cost.
Description of the drawings
With reference to the accompanying drawings and detailed description, to nuclear power station steam generator lower horizontal supporting structure of the present invention and
Its advantage is described in detail.
Fig. 1 is the installation diagram of disclosed steam generator lower horizontal supporting.
Fig. 2 is the structure chart of disclosed steam generator lower horizontal supporting.
Fig. 3 is the structure diagram of nuclear power station steam generator lower horizontal supporting structure of the present invention.
Fig. 4 is the structure diagram of the supporting arrangement of nuclear power station steam generator lower horizontal supporting structure of the present invention.
Fig. 5 is the sectional view of the supporting arrangement of nuclear power station steam generator lower horizontal supporting structure of the present invention.
Fig. 6 is the sectional view of the pedestal of nuclear power station steam generator lower horizontal supporting structure of the present invention.
Specific embodiment
In order to which the goal of the invention, technical solution and its advantageous effects that make the present invention become apparent from, below in conjunction with attached drawing
And specific embodiment, the present invention will be described in further detail.It should be appreciated that the specific reality described in this specification
Mode is applied just for the sake of explaining the present invention, is not intended to limit the present invention.
Referring to Fig. 3, nuclear power station steam generator lower horizontal supporting structure of the present invention includes being respectively arranged on steam generation
Lateral blocked frame 80, the main pipe hot leg center line arranged on steam generator 200 of 100 both sides of main pipe hot leg center line of device 200
Preceding divider 90 on 100 and lateral-supporting platform 50 and forward direction supporting platform 60 on 200 low head of steam generator,
Lateral blocked frame 80 is corresponded with lateral-supporting platform 50, and preceding divider 90 is corresponding with forward direction supporting platform 60.Lateral blocked frame 80 is with before
The supporting arrangement of instantaneous displacement produced by steam generator, side when divider 90 all includes that earthquake or LOCA accident generation can be limited
The structure snd size of the supporting arrangement of divider 80 and preceding divider 90 are all identical, and simply quantity is otherwise varied.
Fig. 4, Fig. 5 and Fig. 6 are referred to, each supporting arrangement includes pedestal 10 and the axial gap tune being located on pedestal 10
Engagement positions.
10 shape of pedestal is ladder shaft-like, and the outer diameter of pedestal 10 gradually successively decreases from back to front, and the leading portion of pedestal big end 102 is
Hollow structure, and 102 leading portion internal diameter of pedestal big end is bigger than pedestal time 103 outer diameter of big end, so that 102 leading portion inner wall of pedestal big end
Semidiameter Δ r is formed between pedestal time 103 outer wall of big end.
Since, there are semidiameter Δ r, and pedestal is big between 102 leading portion inner wall of pedestal big end and pedestal time 103 outer wall of big end
108 thickness of annular region that end 102 is connected with pedestal time big end 103 is t, axial when adjustment bolt 20 is by axial compressive force
Pressure is transferred to annular region 108 by pedestal time big end 103, and semidiameter Δ r is the arm of force of the axial compressive force, annular at this time
Region 108 can generate flexural deformation, that is to say that pedestal 10 has pooling feature, and cushion performance is excellent.
And annular region 108 is preferably processed by forging integration, and the buffering of pedestal is formed by forging process
Performance is best.If pedestal big end 102, pedestal time big end 103 and annular region 108 be combined by way of splicing and
Into since pedestal big end 102, pedestal time big end 103 and the mutual connecting portion of annular region 108 are not to belong to original
Material structure causes deformation performance to reduce and influence the cushion performance of pedestal.
Flexural deformation size is also related for t with annular region thickness, and the smaller flexural deformations of t are bigger, therefore can pass through tune
The thickness t and semidiameter Δ r of the annular region of pedestal are saved to change the cushion performance of pedestal, base construction is simple, easy for installation,
Effectively reduce manufacture and installation cost.The pooling feature of pedestal primarily to cuisine steam generator because of earthquake or LOCA accident
The shock loading generated during generation by instantaneous displacement, so as to ensure reactor coolant loop, steam generator and civil engineering knot
The stability and security of structure.
Axial interval regulator includes adjustment bolt 20, the adjustment bolt locking mechanism being located on pedestal 10 and is opened in
The adjustment threaded hole 101 of 10 front end face of pedestal, adjustment bolt 20 are screwed in adjustment threaded hole 101, screwed in by adjusting bolt 20
Or adjustment threaded hole 101 is screwed out to realize the adjustment of axial gap, adjustment bolt locking mechanism can make adjustment bolt 20 fix nothing
Method rotates.The depth screwed in by adjusting adjustment bolt 20 in adjustment threaded hole 101 can be completed gap and adjust, and effectively shorten
Clearance measurement and the time of adjustment, save time cost and human cost.
In one embodiment of nuclear power station steam generator lower horizontal supporting structure of the present invention, adjustment bolt locking knot
Structure includes clamping screw 30 and the radial indentation 104 being opened on adjustment 101 hole wall of threaded hole of pedestal front end 107.Radially
Notch 104 separates adjustment 101 hole wall of threaded hole of adjacent both sides and the radical length of radial indentation 104 at least compares hole wall
Thickness is big, is provided with axially extending bore 105 on 101 hole wall of adjustment threaded hole of 104 front side of radial indentation, positioned at radial indentation
The locking screw pit 106 coaxial with axially extending bore 105 is provided on the adjustment threaded hole hole wall of 104 rear sides, clamping screw 30 is first worn
It crosses axially extending bore 105 and is screwed into locking screw pit 106, the threaded connection between clamping screw 30 and locking screw pit 106
101 hole wall of adjustment threaded hole that power can oppress positioned at 104 front side of radial indentation tilts, and the 101 hole wall inclination of adjustment threaded hole is led
Cause that adjustment bolt is stuck to rotate.
In one embodiment of nuclear power station steam generator lower horizontal supporting structure of the present invention, radial indentation 104
In pedestal front end 107 close to the one side of 10 front end face of pedestal, positioned at the axial direction of the adjustment threaded hole hole wall of 104 front side of radial indentation
Length is shorter, adjusts the easier inclination of threaded hole hole wall.The radical length of radial indentation is bigger than pedestal front end outer radius, compares pedestal
Front end overall diameter is small, and the radical length of radial indentation can so that greatly adjusting threaded hole hole wall is locking than pedestal front end outer radius
It is easier to tilt under the action of bolt.Locking screw pit 106 is located on the radial symmetric line of radial indentation 104 so that locking screw
The radial direction arm of force of bolt is maximum, and adjustment threaded hole hole wall is easier to tilt under the action of clamping screw.
In one embodiment of nuclear power station steam generator lower horizontal supporting structure of the present invention, pedestal big end 102 is complete
Portion is hollow structure, and such structure is conducive to the processing of pedestal 10, manufacture cost is reduced, during manufacturing, directly after pedestal
The processing of end end face can obtain pedestal big end hollow structure.
In one embodiment of nuclear power station steam generator lower horizontal supporting structure of the present invention, pedestal big end 102 is set
There is mounting flange 40, pedestal is fixed on concrete structure with facilitating.
Referring to Fig. 3, in actual use, nuclear power station steam generator lower horizontal supporting structure of the present invention is specifically installed
Mode is:Pedestal 10 is fixedly mounted on by flange 40 on concrete structure 70, and adjustment bolt 20 and the steam of lateral blocked frame 80 are sent out
The lateral-supporting platform 50 of raw device is opposite to installation, the adjustment bolt 20 of preceding divider 90 and the forward direction supporting platform of steam generator
60 is opposite to installation, and gap is left between adjustment bolt 20 and lateral-supporting platform 50, forward direction supporting platform 60, can be by adjusting
The size for being threaded in or out adjusting the gap of bolt 20.
When reactor coolant loop enters hot shutdown operating mode, testing staff measures adjustment bolt 20 using measuring apparatus
End face to lateral-supporting platform 80 or the gap width of forward direction supporting platform 90, afterwards according to gap acceptance criteria to clearance measurement
Value is correspondingly adjusted, and adjustment bolt 10 is locked by clamping screw 30 after gap adjustment is qualified, to avoid machine
Group operational process in adjustment bolt 20 end face supporting platform correspondings with steam generator between gap width generate change, influence be
The normal operation of system.
In conclusion the pedestal of nuclear power station steam generator lower horizontal supporting structure of the present invention can effectively buffer moment position
The shock loading moved and generated, and gap tune can be completed in the depth screwed in by adjusting adjustment bolt in adjustment threaded hole
It is whole.
Compared with prior art, nuclear power station steam generator lower horizontal supporting structure of the present invention at least has following excellent
Point:
1) clearance measurement simple operation, and measuring result error is smaller;
2) gap adjustment is more convenient, and this structure is effectively shortened the time of clearance measurement and adjustment, when saving
Between cost and human cost;
3) using the pedestal with pooling feature, base construction is simple, and cushion performance is excellent, installs, is easy to maintain, effectively
Reduce manufacture and installation cost.
According to the disclosure and teachings of the above specification, those skilled in the art in the invention can also be to above-mentioned embodiment party
Formula carries out appropriate change and modification.Therefore, the invention is not limited in specific embodiment disclosed and described above, to this
Some modifications and changes of invention should also be as falling into the scope of the claims of the present invention.In addition, although this specification
In used some specific terms, but these terms are merely for convenience of description, do not limit the present invention in any way.
Claims (10)
1. a kind of nuclear power station steam generator lower horizontal supporting structure generates the branch of instantaneous displacement including limitation steam generator
Bearing apparatus, supporting arrangement include pedestal and the axial interval regulator being located on pedestal, it is characterised in that:Outside the pedestal
Shape is ladder shaft-like, and the outer diameter of pedestal gradually successively decreases and forms pedestal big end and pedestal time big end from back to front, pedestal big end
Leading portion is hollow structure, and pedestal big end leading portion internal diameter is bigger than pedestal time big end outer diameter so that pedestal big end leading portion inner wall with
Semidiameter Δ r is formed between pedestal time big end outer wall.
2. nuclear power station steam generator lower horizontal supporting structure according to claim 1, it is characterised in that:The axial direction
Lash adjusting device includes adjustment bolt, the adjustment bolt locking mechanism being located on pedestal and the adjustment for being opened in pedestal front end face
Threaded hole, adjustment bolt are screwed in adjustment threaded hole, are threaded in or out adjustment threaded hole by adjusting bolt to realize between axial direction
The adjustment of gap, adjustment bolt locking mechanism can make adjustment bolt fixation that can not rotate.
3. nuclear power station steam generator lower horizontal supporting structure according to claim 2, it is characterised in that:The adjustment
Bolt locking mechanism is included in the radial indentation being provided on the adjustment threaded hole hole wall of pedestal front end and clamping screw, footpath
The adjustment threaded hole hole wall of adjacent both sides is separated to notch and the radical length of radial indentation is big at least than pore wall thickness,
Axially extending bore, the adjustment threaded hole hole on rear side of radial indentation are provided on adjustment threaded hole hole wall on front side of radial indentation
The locking screw pit coaxial with axially extending bore is provided on wall, clamping screw initially passes through axially extending bore and is screwed into locking screw pit
It is interior.
4. nuclear power station steam generator lower horizontal supporting structure according to claim 3, it is characterised in that:The radial direction
Notch is located at pedestal front end close to the one side of pedestal front end face.
5. nuclear power station steam generator lower horizontal supporting structure according to claim 3, it is characterised in that:The radial direction
The radical length of notch is bigger than pedestal front end outer radius, smaller than pedestal front end overall diameter.
6. nuclear power station steam generator lower horizontal supporting structure according to claim 3, it is characterised in that:The locking
Threaded hole is located on the radial symmetric line of radial indentation.
7. nuclear power station steam generator lower horizontal supporting structure according to claim 1, it is characterised in that:The pedestal
The all hollow structures of big end.
8. nuclear power station steam generator lower horizontal supporting structure according to claim 1, it is characterised in that:The pedestal
Big end is equipped with mounting flange.
9. nuclear power station steam generator lower horizontal supporting structure according to any one of claims 1 to 8, it is characterised in that:
It further includes and is respectively arranged on the lateral blocked frame of steam generator main pipe hot leg center line both sides, arranged on steam generator main pipe hot leg
Preceding divider on center line and the lateral-supporting platform on steam generator low head and forward direction supporting platform, lateral blocked frame
It is corresponded with lateral-supporting platform, preceding divider is corresponding with forward direction supporting platform, and each lateral blocked frame and preceding divider are all included extremely
Few two supporting arrangements.
10. nuclear power station steam generator lower horizontal supporting structure according to claim 9, it is characterised in that:The side
Divider includes two supporting arrangements, and the preceding divider includes three supporting arrangements.
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CN201610417349.4A CN106051722B (en) | 2016-06-15 | 2016-06-15 | Nuclear power station steam generator lower horizontal supporting structure |
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CN201610417349.4A CN106051722B (en) | 2016-06-15 | 2016-06-15 | Nuclear power station steam generator lower horizontal supporting structure |
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CN106051722B true CN106051722B (en) | 2018-05-29 |
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Families Citing this family (4)
Publication number | Priority date | Publication date | Assignee | Title |
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CN108087857B (en) * | 2018-01-04 | 2024-03-01 | 中广核研究院有限公司 | Novel support cushion block for steam generator |
CN109215814B (en) * | 2018-08-01 | 2024-03-22 | 中广核研究院有限公司 | Horizontal support structure for multi-container system |
CN110853784B (en) * | 2019-11-19 | 2022-07-29 | 中国核动力研究设计院 | Pressurized water reactor nuclear power plant stabiliser bearing structure |
CN111140836B (en) * | 2019-12-04 | 2021-12-07 | 深圳中广核工程设计有限公司 | Nuclear power station steam generator sleeve supporting device and installation method thereof |
Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH10220703A (en) * | 1997-02-10 | 1998-08-21 | Ishikawajima Harima Heavy Ind Co Ltd | Conveying method for boiler |
JP2000356697A (en) * | 1999-06-11 | 2000-12-26 | Toshiba Corp | Reactor core shroud inner diameter automatic measuring device |
CN203026161U (en) * | 2012-12-13 | 2013-06-26 | 中国核动力研究设计院 | Cantilever type supporting device of reactor pressure vessel |
CN104121571A (en) * | 2013-04-25 | 2014-10-29 | 中广核工程有限公司 | Lower horizontal bearing structure of steam generator |
CN204201278U (en) * | 2014-07-31 | 2015-03-11 | 中国船舶重工集团公司第七一九研究所 | A kind of supporting pipeline device of adaptability adjustment setting height(from bottom) |
-
2016
- 2016-06-15 CN CN201610417349.4A patent/CN106051722B/en active Active
Patent Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH10220703A (en) * | 1997-02-10 | 1998-08-21 | Ishikawajima Harima Heavy Ind Co Ltd | Conveying method for boiler |
JP2000356697A (en) * | 1999-06-11 | 2000-12-26 | Toshiba Corp | Reactor core shroud inner diameter automatic measuring device |
CN203026161U (en) * | 2012-12-13 | 2013-06-26 | 中国核动力研究设计院 | Cantilever type supporting device of reactor pressure vessel |
CN104121571A (en) * | 2013-04-25 | 2014-10-29 | 中广核工程有限公司 | Lower horizontal bearing structure of steam generator |
CN204201278U (en) * | 2014-07-31 | 2015-03-11 | 中国船舶重工集团公司第七一九研究所 | A kind of supporting pipeline device of adaptability adjustment setting height(from bottom) |
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