CN202170656U - Nuclear power plant arrangement structure - Google Patents
Nuclear power plant arrangement structure Download PDFInfo
- Publication number
- CN202170656U CN202170656U CN2011202353160U CN201120235316U CN202170656U CN 202170656 U CN202170656 U CN 202170656U CN 2011202353160 U CN2011202353160 U CN 2011202353160U CN 201120235316 U CN201120235316 U CN 201120235316U CN 202170656 U CN202170656 U CN 202170656U
- Authority
- CN
- China
- Prior art keywords
- island
- nuclear
- nuclear power
- power station
- conventional island
- 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.)
- Expired - Lifetime
Links
Images
Classifications
-
- 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
Landscapes
- Buildings Adapted To Withstand Abnormal External Influences (AREA)
Abstract
The utility model provides a nuclear power plant arrangement structure which comprises a nuclear island, a conventional island and a first span structure, wherein the first span structure is located between the nuclear island and the conventional island; and equipment and pipes in a transition segment between the nuclear island and the conventional island are arranged in the first span structure. Through the utility model, the construction cost of a whole nuclear power plant is decreased and the workload during safety assessment is decreased.
Description
Technical field
The utility model relates to a kind of nuclear power station arrangement.
Background technology
Along with the development of nuclear energy technology, the application of nuclear power more and more widely.In order to guarantee the safety of nuclear power, usually from defence-in-depth concept, take multiple measure, depth defense refers to the inefficacy in the technology of considering and the organization and administration and the multi-level defense system set up.The depth defense principle is a kind of Safety Design thought of each item activity in production through whole phase in longevity of nuclear power station (comprising retired) in each stage, and each layer defence all must be effectively, and each level all must be considered as last one barrier.Must be appreciated that the at all levels of depth defense all possibly tested in the nuclear power station design, therefore must provide measure to guarantee the realization of its security purpose.
AP1000 is a third generation nuclear power technology, adopts the pressurized water type reactor of Second Ring Road, and it adopts power plant's design of passive safety and simplification, thereby makes nuclear power plant have the good property made, performability and maintainability.Passive safety system is to utilize the physical phenomenon and the principles such as natural circulation, gravity and expansion of compressed gas of almost running into every day in the daily life; Realize the heat discharge of reactor core cooling and containment; Greatly simplified system; Also making operator's time allowance be increased to 72h, is a kind of innovative design.
As shown in Figure 1, in the AP1000 nuclear power technology of prior art, the arrangement of nuclear power station mainly comprise nuclear island 10, with nuclear island 10 next-door neighbour's conventional island 11 and the anti-whipping framework 12 in the conventional island 11.Wherein, nuclear island 10 is that nuclear reactor and the general designation of each system relevant with reactor in the nuclear power plant containment shell mainly comprises nuclear steam supply system, containment spray system and accessory system etc.Conventional island 11 is general names of Turbo-generator Set and ancillary facility and place factory building thereof in the nuclear power station, and its major function is the mechanical energy that the thermal power transfer that nuclear island 10 produces steam is become steam turbine, is transformed into electric energy through generator again.
Be furnished with the changeover portion of nuclear island 10 in the anti-whipping framework 12, comprise the equipment, pipeline of some non-nuclear levels etc. to conventional island 11.Because high energy pipelines such as main steam pipe, main feed water pipe need lead to conventional island 11 from nuclear island 10; Be provided with elbow and piping erection attachment weld etc. on it unavoidably; The broken pipe of high energy such as main steam pipe, main feed water pipe pipeline (as under extreme cases such as SSE earthquake, cyclone) can produce and get rid of pipe and jet phenomenon, has stronger impact force and destructive power.Anti-whipping framework 12 is exactly to be used for resisting that the broken pipe of high energy pipeline produced gets rid of pipe and jet-action.In addition, also be furnished with various other pipelines, cable and the equipment etc. of nuclear island 10 to conventional island 11 in the anti-whipping framework 12, the pipe-line equipment of nuclear level is through installing pipeline, cable and the equipment that jointing transition in changeover portion is non-nuclear level therein.
But this arrangement of prior art has following shortcoming:
Anti-whipping framework 12 is arranged in the conventional island 11; Only play the effect of getting rid of pipe and spraying that the broken pipe of high energy pipeline produces of resisting; The layout of other non-nuclear level pipe-line equipment must be avoided this anti-rejection framework 12 in conventional island 11 steam turbine building, thereby has influenced the layout of conventional island 11 steam turbine building greatly;
Though anti-whipping framework 12 is arranged in the conventional island 11; But its structure is established one's own system; Vertical, the transverse direction of conventional island 11 all separates in the layout upper edge; Thereby cause conventional island 11 main building steam turbine building structural plans to be arranged and be concave-convex type, irregular layout will have a negative impact to conventional island 11 steam turbine building structural entity rigidity; Particularly the high energy pipe arrangement for the AP1000 nuclear power technology disperses more; Adopt the area requirement of anti-whipping framework 12 bigger; The main building structural configuration of conventional island 11 will be more irregular, and the structural configuration of conventional island 11 main buildings that cause thus is unreasonable, and the cross section of structural element is bigger; Steel ratio is higher, and the structural cost of engineering is higher;
When the influencing of assessment conventional island 11 pairs of nuclear islands 10, whole conventional island 11 is one, carries out the heavy complicacy of agent structure deformation analysis amount of calculation under the SSE earthquake operating mode.Especially for similar AP1000 nuclear power technology, not with reference to the conventional island 11 main building structures of the new nuclear power station of engineering, its conventional island 11 steam turbine building are arranged will be along with design process need constantly be adjusted and improved.Because anti-whipping structure 12 is positioned within conventional island 11 main buildings; The conventional island 11 main buildings adjustment of arranging each time all will be carried out once the security evaluation to the influence of nuclear island 10 to the whole conventional island 11 main building structures that comprise anti-whipping structure 12; Its workload is very heavy, and main is to impact whole nuclear power engineering design schedule;
During the influencing of assessment conventional island 11 pairs of nuclear islands 10; The conventional island 11 main building agent structure scale of constructions that comprise anti-whipping framework 12 are huge; Layout is irregular, and the influence factor of its result of calculation is very many, and is reliable in order to guarantee engineering safety; The calculating of reply total all adopts conservative calculating means to consider that promptly all influence factors accomplish the design of whole conventional island 11 main building agent structures, thereby causes the construction costs of conventional island 11 main building structures of nuclear power station higher;
Because the volume of anti-whipping framework 12 is limited; Non-nuclear level equipment in some changeover portions of nuclear power station is also had to be arranged in the factory building of nuclear island 10; Make the factory building volume of nuclear island 10 bigger; And the factory building unit structure cost of nuclear island 10 is far above structural units's cost of conventional island 11, thereby increased the cost of whole nuclear power engineering.
The utility model content
The technical problem that the utility model will solve provides a kind of nuclear power station arrangement, and the anti-whipping framework of solution is unreasonable to the conventional island structural configuration that influence caused of conventional island, construction costs is high, arrange the excessive problem of adjusted security evaluation workload.
For solving the problems of the technologies described above; The utility model provides a kind of nuclear power station arrangement; Comprise nuclear island and conventional island; Also comprise and between said nuclear island and conventional island, first stride structure, equipment in the changeover portion between said nuclear island and the conventional island and pipe arrangement are striden in the structure said first, and said first strides structure adopts the reinforced concrete frame shear wall structure.
Alternatively, the pipeline in the said changeover portion comprises main steam pipe, strides in the structure said first, and said main steam pipe is disposed with energy-dissipating device, concrete wall and pillar outward.
Alternatively, stride in the structure said first, also be provided with shear wall in the said pillar outside, the height of said shear wall is less than the height of said pillar, and the bearing of trend of said shear wall is perpendicular to the bearing of trend of said concrete wall.
Alternatively, the pipeline in the said changeover portion comprises main feed water pipe, strides in the structure said first, is provided with shear wall around the said main feed water pipe, and the thickness of the floor in its jet-action regional extent is more than or equal to 250mm.
Alternatively; Equipment in the said changeover portion comprises active equipment and cold equipment under the accident condition; Said first strides structure is divided into a plurality of intervals, and the slab thickness that wherein is provided with the interval of active equipment under the accident condition is greater than the slab thickness that is provided with the interval of cold equipment under the accident condition.
Alternatively, saidly be provided with that the interval outer periphery of active equipment is equipped with the barrier shield of thickness more than or equal to 600mm under the said accident condition, said barrier shield is built into by concrete block.
Alternatively, the said slab thickness that is provided with the interval of active equipment under the said accident condition is more than or equal to 450mm, and the said slab thickness that is provided with the interval of cold equipment under the accident condition is more than or equal to 410mm and less than 450mm.
Alternatively, said first to stride structure be sandwich construction.
Alternatively, said first strides that structure is positioned on the ground, underground or part is positioned on the ground, and part is positioned at underground.
Compared with prior art, the utlity model has following advantage:
In the nuclear power station arrangement of the utility model embodiment, the changeover portion between nuclear island to the conventional island is arranged in first strides in the structure, said first to stride structure be the absolute construction between nuclear island and the conventional island, wherein accommodates equipment and pipeline in the changeover portion.Through adopting first to stride structure; Can be with the anti-whipping framework cancellation in the conventional island in the prior art; Changeover portion between nuclear island and the conventional island is fully independent and be placed on first and stride the structure in conventional island; Can make conventional island agent structure layout more rule help reducing construction costs with rationally, and the workload when making the assessment conventional island to the influencing of nuclear island descends greatly.
Further, stride in the structure first, main steam pipe is disposed with energy-dissipating device, concrete wall and pillar outward, bears the whipping power that the broken pipe of main steam pipe produces; And can also be provided with shear wall in the pillar outside, and the height of shear wall is less than the height of pillar, and the bearing of trend of shear wall is perpendicular to the bearing of trend of concrete wall, thereby can reduce the calculated height of pillar, improves the anti-main steam pipe whipping ability of pillar.
In addition, stride in the structure, also around main feed water pipe, be provided with shear wall, and increased the thickness of the floor in main feed water pipe jet-action scope, bear the jet power of main feed water pipe with this first.
In addition, first strides and comprises a plurality of intervals in the structure, and each interval concrete wall can have different thickness with floor, and its concrete thickness can be confirmed according to the pipeline and the device type that are arranged on wherein.In the present embodiment; The interval that is provided with active equipment under the accident condition is provided with the barrier shield of thickness more than or equal to 600mm on every side; Its slab thickness is more than or equal to 450mm; Thereby help potential radioactive substance is constrained in this interval, avoid its other intervals on every side that extend influence.
Description of drawings
Fig. 1 is the plane structure sketch map of a kind of nuclear power station arrangement of prior art;
Fig. 2 is the plane structure sketch map of the nuclear power station arrangement of the utility model embodiment;
Fig. 3 is that first of the utility model embodiment strides in the structure-the part plane structure chart of 0.04m layer;
Fig. 4 is that first of the utility model embodiment strides in the structure-the part plane structure chart of 10.29m layer;
Fig. 5 is the part plane structure chart that first of the utility model embodiment strides 5.299m layer in the structure;
Fig. 6 is that first of the utility model embodiment strides in the structure-another part plane structure chart of 0.04m layer;
Fig. 7 is another part plane structure chart that first of the utility model embodiment strides 5.299m layer in the structure;
Fig. 8 is the part plane structure chart that first of the utility model embodiment strides 10.709m layer in the structure.
The specific embodiment
In the prior art; The changeover portion of nuclear island to conventional island is arranged on often to be prevented in the conventional island can the layout of conventional island being exerted an influence in the whipping framework, makes that the arrangement of conventional island is irregular, rigidity is relatively poor; Increased conventional island area, improved construction costs; And, need to prevent that the whipping framework counts during to the influencing of nuclear island at the assessment conventional island, make amount of calculation very big.
In the nuclear power station arrangement of the utility model embodiment, the changeover portion between nuclear island to the conventional island is arranged in first strides in the structure, said first to stride structure be the absolute construction between nuclear island and the conventional island, wherein accommodates equipment and pipeline in the changeover portion.Through adopting first to stride structure; Can be with the anti-whipping framework cancellation in the conventional island in the prior art; Changeover portion between nuclear island and the conventional island is fully independent and be placed on first and stride the structure in conventional island; Can make conventional island agent structure layout more rule help reducing construction costs with rationally, and the workload when making the assessment conventional island to the influencing of nuclear island descends greatly.
Further, stride in the structure first, main steam pipe is disposed with energy-dissipating device, concrete wall and pillar outward, bears the whipping power that the broken pipe of main steam pipe produces; And can also be provided with shear wall in the pillar outside, and the height of shear wall is less than the height of pillar, and the bearing of trend of shear wall is perpendicular to the bearing of trend of concrete wall, thereby can reduce the calculated height of pillar, improves the anti-main steam pipe whipping ability of pillar
In addition, stride in the structure, also around main feed water pipe, be provided with shear wall, and increased the thickness of the floor in main feed water pipe jet-action scope, bear the jet power of main feed water pipe with this first.
In addition, first strides and comprises a plurality of intervals in the structure, and each interval concrete wall can have different thickness with floor, and its concrete thickness can be confirmed according to the pipeline and the device type that are arranged on wherein.In the present embodiment; The interval that is provided with active equipment under the accident condition is provided with the barrier shield of thickness more than or equal to 600mm on every side; Its slab thickness is more than or equal to 450mm; Thereby help potential radioactive substance is constrained in this interval, avoid its other intervals on every side that extend influence.
Below in conjunction with specific embodiment and accompanying drawing the utility model is described further, but should limit the protection domain of the utility model with this.
Fig. 2 shows the integral planar structural representation of the nuclear power station arrangement of present embodiment; Comprise that nuclear island 20, conventional island 21 and first stride structure 22; Wherein first stride structure 22 between nuclear island 20 and conventional island 21; First strides equipment and the pipeline in the changeover portion that is furnished with in the structure 22 between nuclear island 20 and the conventional island 21, like main steam pipe, main feed water pipe, cable, CCS heat interchanger, BDS heat interchanger, CCS pump, BDS EDI module, ICP frequency conversion equipment, BDS steam generator blowdown exchanger, BDS system ionization desalination unit or the like.
In the present embodiment, first to stride structure 22 are the buildings that are independent of outside nuclear island 20 and the conventional island 21, mainly adopt the reinforced concrete frame shear wall structure, and carried out relevant structural configuration and designed with seismic design, anti-cyclone.In addition, first to stride structure 22 can be sandwich construction, and each layer can be divided into a plurality of intervals, is used to be provided with corresponding apparatus, pipeline etc.First strides that each layer in the structure 22 can be positioned on the ground, underground or part layer is positioned at the overground part layering and is positioned at underground.
Through first stride structure 22 layout, nuclear island 20 and conventional island 21 are kept apart fully, both nuclear island 20 was played a protective role, also conventional island 21 is played a protective role.For AP 1000 nuclear power technologies, the equipment of the non-nuclear level of the part in its nuclear island 20 can be arranged in first and stride in the structure 22, has reduced the volume of the higher nuclear island 20 of cost greatly.Stride first simultaneously and also can both arrange non-nuclear level equipment and pipeline in the nuclear island 20 in the structure 22; Arrange equipment component and pipeline and the interface between the two in the conventional island 21 again; Increased the utilization rate of building volume; Thereby make the total measurement (volume) of whole nuclear power station agent structure reduce, and the volume of nuclear island reduces, and the total cost of nuclear power station reduces.
After having adopted first to stride structure 22, the anti-whipping framework in the conventional island 21 is cancelled, and makes that the plane arrangement structure of conventional island 21 is regular more with rationally.Particularly for AP 1000 nuclear power technologies, the structural configuration of the rational conventional island 21 of rule has reduced the interface of structural element, makes the engineering structures cost reduce greatly.
It is complete independent structures that in the present embodiment first striden structure 22; Need not to consider the technology arrangement and the traffic aisle of conventional island 21 as the anti-whipping frame arrangement of prior art; Therefore its structural configuration is free; Make that structural configuration and form of structure are more reasonable, thereby reduce the cost of Structural Engineering.
Because first strides structure 22 nuclear island 20 and 22 two structures of conventional island are kept apart fully; Thereby during the influencing of assessment conventional island 21 pairs of nuclear islands 20, only need stride structure 22 to first and assess, any modification of conventional island 21 simultaneously and adjustment all do not influence the structure of nuclear island 20; Need not to stride structure 22 and carry out the nuclear power security evaluation again first; Therefore first stride structure 22 introducing, reduced the scope of assessment of nuclear power safety greatly, reduced that conventional island 21 is continued to optimize adjustment and the assessment number of times that causes; Simplify the design work amount, accelerated the progress of whole nuclear power engineering design.
The nuclear safety assessment need be carried out the elastoplasticity checking computations to structure under disasters such as SSE earthquake, cyclone; And structure done strictness, harsh assessment, and stride structure 22 through introducing first, reduced the scope of nuclear safety assessment greatly; Also reduced structure design-calculated influence factor; Make structure design more safe and reliable, the calculating of total is more accurate, helps further reducing the construction costs of nuclear power station conventional island 21 agent structures.
In addition; First strides structure 22 can adopt reinforced concrete structure, steel concrete wall column; And can come effectively have the equipment and the pipeline of trace-level activity in the shielding changeover portion through the thickness that strengthens floor, thus can replace the steel plate isolation structure, reduce construction costs.
Fig. 3 to Fig. 8 shows the part plane structure chart that first of present embodiment is striden each layer in the structure, is described in detail below in conjunction with Fig. 3 to Fig. 8.Need to prove; The unit of the concrete numerical value that is marked among Fig. 3 to Fig. 8 is mm; Though provided concrete numerical value in the drawings, in other specific embodiments, according to the needs of practical application; Can regulate given concrete numerical value, should not regard qualification as protection domain at this.In addition; The label that has the band circle in the left side of Fig. 3 to Fig. 8; Like T.A, T.B, T.C, T.D, T.E, T.F, wherein identical label is represented the interior same reference line along horizontal direction of horizontal plane, and the downside of Fig. 3 to Fig. 8 has the label of band circle; As T.0, T.1, wherein identical label is represented in the horizontal plane same reference line along the longitudinal direction.
With reference to figure 3; Fig. 3 be first stride in the structure-the 0.04m layer (represent underground among this paper by negative sign; Positive sign is represented on the ground) the part plane structure, first strides and is provided with main steam pipe 30 in the structure, main steam pipe 30 outer energy-dissipating device 31, concrete wall 32 and the pillars 33 of being disposed with.Getting rid of of producing when considering main steam pipe 30 broken pipes managed and jet-action, and energy-dissipating device 31 can cushion and absorb the destructive power that produces when getting rid of pipe, and the feasible strike kinetic energy that gets rid of pipe reduces, thereby minimizing acts on the power on the concrete wall 32.Further, through at concrete wall 32 arranged outside pillars 33, can further keep out brokenly whipping power when managing.In addition, jet power can be born by the body of wall of conventional island steam turbine building agent structure, and active force is separately born by two kinds of structures, is that structure all is in a safe condition, and guarantees the safety of nuclear island.
Fig. 4 shows-the part plane structure of 10.29m layer, combine Fig. 3 simultaneously, and the outside of pillar 33 side of concrete wall 32 (promptly away from) is provided with shear wall 34, and its height is less than the height of pillar 33, and its bearing of trend is perpendicular to the bearing of trend of concrete wall 32.In other words, shear wall 34 has withstood the latter half of pillar 33, helps bearing the pipe effect of getting rid of that main steam pipe 30 broken pipes produce, and on the other hand, can also reduce the calculated length of pillar 33.
With reference to figure 5; Fig. 5 is the part plane structure of 5.299m layer; In the present embodiment first striden the main feed water pipe (not shown) that also is provided with in the structure in the changeover portion; Be provided with shear wall around the main feed water pipe, and the thickness of the floor 35 in its jet-action regional extent is more than or equal to 250mm, the jet-action when bearing the broken pipe of main feed water pipe.
First strides structure and is divided into a plurality of intervals in the present embodiment; Be respectively applied for corresponding pipeline and the equipment etc. of being provided with; Wherein, the slab thickness that is provided with the interval of active equipment under the accident condition is greater than the slab thickness that is provided with the interval of cold equipment under the accident condition.To Fig. 8, Fig. 6 is-plane structure of 0.04m layer with reference to figure 6, and Fig. 7 is the plane structure of 5.299m layer, and Fig. 8 is the plane structure of 10.709m layer.Wherein, Be provided with active equipment under the accident condition in interval 40, like BDS steam generator blowdown exchanger, BDS systematic electricity desalination unit etc., owing to have the radioactivity of trace in the state of accident; For radioactive substance is shielded in interval 40; Interval 40 outer periphery is equipped with the barrier shield 36 of thickness more than or equal to 600mm, and barrier shield 36 is built into by concrete block, and the thickness of interval 40 floor 37 is more than or equal to 450mm.And the interval beyond interval 40 promptly is provided with the interval of cold equipment under the accident condition (like CCS heat interchanger, BDS heat interchanger, CCS pump, ICP frequency conversion equipment etc.), and its slab thickness is more than or equal to 410mm, less than 450mm.
Through different intervals being provided with the floor and the barrier shield of different-thickness, can the shielding of the radioactive substance under the accident condition be constrained in the less interval on the one hand, help reducing the cost of whole engineering on the other hand again.
Stride form of structure and layout feature for first in the present embodiment, the inventor has adopted the Pushover analytical method to carry out the checking computations of SSE geological process elastic-plastic deformation.Pushover combines with earthquake response spectrum; Be a kind of simplification computational methods of structural nonlinear seismic response; Can calculate structure from linear elasticity, surrender until internal force, distortion, plastic hinge position and the corner of limit collapsed state; Find out the weak part of structure, even can draw than the more important information of Nonlinear time-history analysis.Analyze through Pushover, first stride structure through what optimize and revise in the present embodiment, can bear predetermined earthquake intensity, guaranteed that first strides the safe and reliable of structure.
In addition, the inventor has also carried out the analysis of cyclone effect.Cyclone mainly contains two aspects to the destruction that nuclear power station produces: the percussion of hypervelocity wind; The cyclone center through the time the unexpected air pressure that produces fall.Stride cyclone wind speed field numerical model that structure recommends through national nuclear safety method and popular in the world wind speed field numerical model at present in conjunction with first, and two kinds of numerical models are contrasted, provide the corresponding field of pressure numerical model of wind speed field numerical model; Study wind speed field and field of pressure binding mode again, obtain the computational methods of computing node wind load time-histories building.Design basis parameter according to zone, factory site cyclone in conjunction with the result of study of shapefactorofwindload, calculates the cyclone load that conventional island first is striden.Through the deformation analysis to the cyclone load action, the member that local adjustment does not meet the demands guarantees that not auxiliary to nuclear island, attached factory building exerts an influence.
To sum up; First of present embodiment is striden structure can solve dynamo-electric technology Layout Problem such as equipment, pipeline, cable testing bridge, HVAC airduct between nuclear island and the conventional island steam turbine building agent structure; For the device security stable operation of conventional island provides the works fine environment; Have for nuclear island simultaneously and formed a safe and reliable barrier; Isolate conventional island changeover portion under extreme conditions (such as SSE earthquake, cyclone, the broken pipe of conventional island equipment etc.), to the influence of nuclear island and the generation of conventional island main building, for safely and steadily running of nuclear power plant provides safeguard.
In first some equipment of striding and pipeline, there are some micro-radiant matters in addition, also can these micro-radiant matters be constrained in certain zone, prevent its environment around extending influence through first structural configuration of striding.
Though first in the present embodiment striden structure and be applied to AP 1000 nuclear power technologies, this thought also can extend in other nuclear power technologies.
Though the utility model with preferred embodiment openly as above; But it is not to be used for limiting the utility model; Any those skilled in the art are in spirit that does not break away from the utility model and scope; Can make possible change and modification, so the protection domain of the utility model should be as the criterion with the scope that the utility model claim is defined.
Claims (9)
1. nuclear power station arrangement; Comprise nuclear island and conventional island; It is characterized in that; Also comprise and between said nuclear island and conventional island, first stride structure, equipment in the changeover portion between said nuclear island and the conventional island and pipe arrangement are striden in the structure said first, and said first strides structure adopts the reinforced concrete frame shear wall structure.
2. nuclear power station arrangement according to claim 1 is characterized in that the pipeline in the said changeover portion comprises main steam pipe, strides in the structure said first, and said main steam pipe is disposed with energy-dissipating device, concrete wall and pillar outward.
3. nuclear power station arrangement according to claim 2; It is characterized in that; Stride in the structure said first; Also be provided with shear wall in the said pillar outside, the height of said shear wall is less than the height of said pillar, and the bearing of trend of said shear wall is perpendicular to the bearing of trend of said concrete wall.
4. nuclear power station arrangement according to claim 1; It is characterized in that the pipeline in the said changeover portion comprises main feed water pipe, stride in the structure said first; Be provided with shear wall around the said main feed water pipe, the thickness of the floor in its jet-action regional extent is more than or equal to 250mm.
5. nuclear power station arrangement according to claim 1; It is characterized in that; Equipment in the said changeover portion comprises active equipment and cold equipment under the accident condition; Said first strides structure is divided into a plurality of intervals, and the slab thickness that wherein is provided with the interval of active equipment under the accident condition is greater than the slab thickness that is provided with the interval of cold equipment under the accident condition.
6. nuclear power station arrangement according to claim 5 is characterized in that, saidly is provided with that the interval outer periphery of active equipment is equipped with the barrier shield of thickness more than or equal to 600mm under the said accident condition, and said barrier shield is built into by concrete block.
7. nuclear power station arrangement according to claim 5; It is characterized in that; The said slab thickness that is provided with the interval of active equipment under the said accident condition is more than or equal to 450mm, and the said slab thickness that is provided with the interval of cold equipment under the accident condition is more than or equal to 410mm and less than 450mm.
8. nuclear power station arrangement according to claim 1 is characterized in that, said first to stride structure be sandwich construction.
9. nuclear power station arrangement according to claim 1 is characterized in that, said first strides that structure is positioned on the ground, underground or part is positioned on the ground, and part is positioned at underground.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN2011202353160U CN202170656U (en) | 2011-07-05 | 2011-07-05 | Nuclear power plant arrangement structure |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN2011202353160U CN202170656U (en) | 2011-07-05 | 2011-07-05 | Nuclear power plant arrangement structure |
Publications (1)
Publication Number | Publication Date |
---|---|
CN202170656U true CN202170656U (en) | 2012-03-21 |
Family
ID=45828851
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN2011202353160U Expired - Lifetime CN202170656U (en) | 2011-07-05 | 2011-07-05 | Nuclear power plant arrangement structure |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN202170656U (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN102287062A (en) * | 2011-07-05 | 2011-12-21 | 中国电力工程顾问集团华东电力设计院 | Arrangement structure of nuclear power station |
CN103216123A (en) * | 2013-04-16 | 2013-07-24 | 中国电力工程顾问集团华东电力设计院 | Nuclear power conventional island whipping prevention device |
CN104131714A (en) * | 2014-06-30 | 2014-11-05 | 中国核电工程有限公司 | Method for arranging first span of nuclear power station steam turbine plant |
-
2011
- 2011-07-05 CN CN2011202353160U patent/CN202170656U/en not_active Expired - Lifetime
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN102287062A (en) * | 2011-07-05 | 2011-12-21 | 中国电力工程顾问集团华东电力设计院 | Arrangement structure of nuclear power station |
CN103216123A (en) * | 2013-04-16 | 2013-07-24 | 中国电力工程顾问集团华东电力设计院 | Nuclear power conventional island whipping prevention device |
CN103216123B (en) * | 2013-04-16 | 2015-04-15 | 中国电力工程顾问集团华东电力设计院 | Nuclear power conventional island whipping prevention device |
CN104131714A (en) * | 2014-06-30 | 2014-11-05 | 中国核电工程有限公司 | Method for arranging first span of nuclear power station steam turbine plant |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
CN102287062B (en) | Arrangement structure of nuclear power station | |
CN103850483A (en) | Main machine hall group arrangement method of nuclear power plant | |
Markou et al. | Seismic assessment of small modular reactors: NuScale case study for the 8.8 Mw earthquake in Chile | |
Sextos et al. | Seismically induced uplift effects on nuclear power plants. Part 2: Demand on internal equipment | |
Stewart et al. | Economic solution for low carbon process heat: A horizontal, compact high temperature gas reactor | |
Parsi et al. | Seismic isolation: A pathway to standardized advanced nuclear reactors | |
CN202170656U (en) | Nuclear power plant arrangement structure | |
Frano et al. | Preliminary evaluation of seismic isolation effects in a Generation IV reactor | |
Meiswinkel et al. | Design and construction of nuclear power plants | |
CN108193906A (en) | A kind of nuclear island factory building arrangement | |
Bangash | Structures for nuclear facilities: analysis, design, and construction | |
Hyun et al. | Seamless remote dismantling system for heavy and highly radioactive components of Korean nuclear power plants | |
Oh et al. | A new design concept and seismic margin assessment for a spent fuel storage system | |
Forni et al. | Seismic isolation of lead-cooled reactors: the European project SILER | |
Forni et al. | Seismic-Initiated events risk mitigation in LEad-cooled Reactors: the SILER Project | |
CN106340330B (en) | A kind of underground nuclear power station main building group step layout design method | |
Mir et al. | Guidelines for Implementing Seismic Base Isolation in Advanced Nuclear Reactors | |
CN108766608B (en) | SC fractal structure of shielding wall of nuclear power station | |
CN115478721B (en) | Nuclear island factory building structure is arranged to nuclear power plant list heap | |
Kammer et al. | Underground nuclear power plants with surface turbine generators | |
Kunze et al. | Underground nuclear energy complexes: technical and economic advantages | |
Song et al. | Shaking Table Testing of a Scaled Nuclear Power Plant Structure with Base Isolation | |
Wei et al. | Evaluation of the Additional Stress on Adjacent Tunnel Shafts Induced by Foundation Pit Excavation | |
Pinto | A survey of the underground siting of nuclear power plants | |
Myers et al. | Underground nuclear parks and the continental SuperGrid |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
C14 | Grant of patent or utility model | ||
GR01 | Patent grant | ||
AV01 | Patent right actively abandoned |
Granted publication date: 20120321 Effective date of abandoning: 20130313 |
|
RGAV | Abandon patent right to avoid regrant |