CN103821766A - Normal afterheat guide-out pump for AP 1000 nuclear power technology - Google Patents
Normal afterheat guide-out pump for AP 1000 nuclear power technology Download PDFInfo
- Publication number
- CN103821766A CN103821766A CN201410079893.3A CN201410079893A CN103821766A CN 103821766 A CN103821766 A CN 103821766A CN 201410079893 A CN201410079893 A CN 201410079893A CN 103821766 A CN103821766 A CN 103821766A
- Authority
- CN
- China
- Prior art keywords
- pump
- bearing
- nuclear power
- power technology
- waste heat
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
Images
Abstract
The invention relates to a normal afterheat guide-out pump applicable to a power plant adopting an AP 1000 nuclear power technology. Major components of the normal afterheat guide-out pump for the AP 1000 nuclear power technology comprise a fluid dynamic pressing sliding bearing, a press-out chamber cover plate, an impeller, a pump body, a press-out chamber, a pump cover, a throat bushing, a sealing component and a bearing, wherein the pump body and the press-out chamber form an energy collecting function component, the press-out chamber and the press-out chamber cover plate adopt conical surface matching and are connected through screw bolts, the impeller is arranged in the pump body, the suck-in opening side of the impeller is provided with a prepositive fluid dynamic pressing sliding bearing, and the upper end of a pump shaft is provided with a bearing component. The pump provided by the invention has the characteristics that the structure is simple, safety and reliability are realized, the efficiency is high, the integral anti-seismic performance is good, and the maintenance is convenient and fast; the normal afterheat guide-out pump can meet high-temperature high-pressure and harsh radiation environment requirements of the power plant and the strong seismic oscillation requirements.
Description
Technical field
The present invention relates to a kind of vertical cantilever pump, especially a kind of normal waste heat that is applicable to adopt the power plant of AP1000 nuclear power technology to use is derived pump.
Background technique
Adopting the normal waste heat in the power plant of AP1000 nuclear power technology to derive pump, is one of visual plant in the normal waste heat guiding system of such nuclear power plant.It is nuclear safety triplex that aforementioned normal waste heat is derived pump, is positioned at the auxiliary plant of power plant, and the function that during the normal shutdown of execution power plant, in reactor coolant loop, waste heat is derived, plays an important role to a class safe operation of power plant that adopts AP1000 nuclear power technology.
Shortcomings on domestic common pump technology at present:
First: pump rotor, because the effect meeting of radial load is in the fault that occurs in varying degrees wear ring " locking ", can not meet the reliable trouble-free service condition of npp safety equipment long-term safety;
Second: in the running environment under the hot operating mode of high temperature, cannot guarantee that bearing is steady, long-time running reliably;
The the 3rd: after violent earthquake, cannot guarantee the functional completeness of pump group;
The the 4th: under harsh radiation environment, can not guarantee the integrity of pressure boundary.
Summary of the invention
The object of this invention is to provide a kind of structural safety, reliable, efficient pump, this pump can meet normal waste heat derives the requirements of pump.
For achieving the above object, the technical solution used in the present invention is: AP1000 nuclear power technology is derived pump with normal waste heat, critical piece comprises Oil Wedge Hydrodynamic Bearing, delivery chamber cover plate, impeller, the pump housing, delivery chamber, pump cover, throat's lining, sealed member, bearing, the pump housing and delivery chamber form collection of energy functional part, delivery chamber and delivery chamber cover plate adopt cone match, and are connected by bolt; Impeller is installed in the pump housing, and suction eye side arranges preposition Oil Wedge Hydrodynamic Bearing; Pump shaft upper end is provided with bearing part, and pump shaft is connected with motor by coupling.
The described pump housing is adopted as the loop configuration pump housing.
Described Oil Wedge Hydrodynamic Bearing adopts self-lubricating structure, and designs the running clearance of 0.35-0.402mm and take surface through cure process measure.
Described delivery chamber and delivery chamber cover plate adopt forging molding, the moulding of numerical control machining center time processing.
On described pump shaft, by key, throat's lining is installed; Throat's bushing design becomes maze-type structure, between pump shaft and throat's lining, some throttle clearance is set, and makes fluid head decline and reduces fluid leakage, the mechanical seal parts in protection Seal cage through throttling repeatedly.
Described coupling adopts extended type flexible membrane coupling, this coupling is divided into the mounting disc of pump end, lengthens spacing shaft and motor side mounting disc, the mounting disc of pump end, lengthen spacing shaft mounting disc is connected successively with motor side, the mounting disc of pump end is connected with pump shaft by key, and motor side mounting disc is connected with motor output shaft by key.
Described bearing part comprises bearing housing, bearing and bearing box, bearing adopts the angular contact ball bearing of a pair of face-to-face configuration, angular contact ball bearing is set with bearing box outward, bearing and bearing box are arranged on bearing housing inside, between bearing housing and pump cover, support with middle linkage section, and bearing housing is connected with pump cover by bolt.
The present invention is simple in structure, has following several respects outstanding feature:
1. the present invention is split-type structural by the part design of carrying out collection of energy function, be the pump housing and delivery chamber, like this, the pump housing is out of shape in factor impacts such as earthquake, the temperature difference, impact, pipe weights, but can not affect the gap between static element and rotating component, there will not be rotor locking phenomenon.
2. delivery chamber adopts forging molding, and inner flow passage adopts digital control processing, has improved the surface finishment of overcurrent part, thereby has improved hydraulic efficiency, and Forging Technology has guaranteed the requirement of strength of part itself simultaneously.
3. change traditional impeller abrasion-proof ring into Oil Wedge Hydrodynamic Bearing structure and improved rotating stability, reduce the vibration of pump.
4. seal chamber front portion arranges throat's lining, can effectively reduce amount of leakage, improves the efficiency of pump.
5. this pump arranges extended type flexible membrane coupler structure, safe and reliable, lengthens spacing shaft by dismounting, can not remove motor and just can keep in repair easily sealed member and bearing part.
accompanying drawing explanation:
Accompanying drawing 1 is the subdivision structural representation of normal waste heat derivation pump for invention AP1000 nuclear power technology heap type.
Accompanying drawing 2 is the impeller Oil Wedge Hydrodynamic Bearing structural representation of normal waste heat derivation pump for invention AP1000 nuclear power technology heap type.
Accompanying drawing 3 is normal waste heat derivation pump delivery chamber Split type structure schematic diagram for invention AP1000 nuclear power technology heap type.
Throat's bush structure schematic diagram that accompanying drawing 4 is led with normal waste heat for invention AP1000 nuclear power technology heap type.
Accompanying drawing 5 is normal waste heat derivation pump bearing modular construction schematic diagram for invention AP1000 nuclear power technology heap type.
The extended type flexible membrane coupler structure schematic diagram that accompanying drawing 6 is led with normal waste heat for invention AP1000 nuclear power technology heap type.
In figure: Oil Wedge Hydrodynamic Bearing 1, delivery chamber cover plate 2, impeller 3, the pump housing 4, delivery chamber 5, pump cover 6, throat's lining 7, pump shaft 8, middle linkage section 9, bearing 10, bearing box 11, bearing housing 12, pump end mounting disc 13, lengthen spacing shaft 14, motor side mounting disc 15, motor output shaft 16.
Embodiment
Below in conjunction with accompanying drawing, the present invention is described in further details.
As shown in Figure 1, AP1000 nuclear power technology heap type provided by the invention derives pump with normal waste heat.As shown in Figure 1, this pump is vertical, single-stage, single suction, cantilever, the structural type of subdivision radially, and working medium is sucked by pump bottom, and level is discharged.This pump critical piece comprises Oil Wedge Hydrodynamic Bearing 1, delivery chamber cover plate 2, impeller 3, the pump housing 4, delivery chamber 5, pump cover 6, throat's lining 7, pump shaft 8, middle linkage section 9, bearing 10, bearing box 11, bearing housing 12 etc.; The function of carrying out collection of energy is Split type structure, be divided into the pump housing 4 and delivery chamber 5, the pump housing 4 is annular, this is simple in structure, and all directions thermal expansion is even in the time being heated, can guarantee the relative gap between the each parts in the inner chamber of the pump housing 4, realize the optimal movement state of rotatable parts, guarantee the stable operation of pump group.
As shown in Figure 2, impeller is installed in the pump housing, impeller 3 is provided with Oil Wedge Hydrodynamic Bearing 1 in suction port side, it is self-lubricating structure, design the running clearance of 0.35-0.402mm and take surface through cure process measure, the rigidity of liquid film and integrity while guaranteeing to move, guarantee that pump running is more reliable and more stable.
As shown in Figure 3, delivery chamber 5 and the further split of delivery chamber cover plate 2, the two adopts cone match, is bolted, and can effectively reduce leakage.Delivery chamber 5 and delivery chamber cover plate 2 adopt forging molding, the moulding of numerical control machining center time processing, and this kind of comparable conventional cast technique of method elevator pump efficiency 2%-4%, has met the security requirement of nuclear power station to this equipment matched power restriction.
As accompanying drawing 4; throat's lining 7 is installed on pump shaft 8; throat's lining 7 is designed to maze-type structure; between pump shaft and throat's lining, many throttle clearance are set; make fluid head decline through throttling repeatedly and reduce fluid leakage; protect the mechanical seal parts in Seal cage, and improved the efficiency of pump.
As accompanying drawing 5, pump shaft upper end is provided with bearing part, and bearing part mainly comprises bearing 10, bearing box 11 and bearing housing 12, and bearing adopts pair of horns contact ball bearing, and this diagonal angle contact ball bearing adopts grease lubrication mode lubricated, effectively minification.Angular contact ball bearing is set with bearing box 11 outward, bearing 10 and bearing box 11 are arranged on bearing housing 12 inside, bearing box structure can be for convenience detach, meet the needs of power plant's maintenance, between this bearing housing 12 and pump cover 6, support with middle linkage section 9, and bearing housing is connected with pump cover by bolt.
As accompanying drawing 6, extended type flexible coupling, coupling is divided into pump end mounting disc 13, lengthens spacing shaft 14 and motor side mounting disc 15, the mounting disc of pump end, lengthen spacing shaft mounting disc is connected successively with motor side, the mounting disc of pump end is connected with pump shaft 8 by key, and motor side mounting disc is connected with motor output shaft 16 by key.In the time of maintenance pump, the motor that can not dismantle the pump housing 4 and top driven pump keeps in repair sealed member and bearing part, can arrive object rapidly and efficiently.
Claims (7)
1.AP1000 nuclear power technology is derived pump with normal waste heat, critical piece comprises Oil Wedge Hydrodynamic Bearing (1), delivery chamber cover plate (2), impeller (3), the pump housing (4), delivery chamber (5), pump cover (6), throat's lining (7), pump shaft (8), bearing (10), it is characterized in that: the pump housing (4) and delivery chamber (5) form collection of energy functional part, delivery chamber (5) and delivery chamber cover plate (2) adopt cone match, and are connected by bolt; Impeller is installed in the pump housing, and impeller (3) suction port side arranges preposition Oil Wedge Hydrodynamic Bearing (1); Pump shaft upper end is provided with bearing part, and pump shaft (8) is connected with motor by coupling.
2. AP1000 nuclear power technology according to claim 1 is derived pump with normal waste heat, it is characterized in that: the described pump housing (4) is adopted as the loop configuration pump housing.
3. AP1000 nuclear power technology according to claim 1 is derived pump with normal waste heat, it is characterized in that: described Oil Wedge Hydrodynamic Bearing (1) adopts self-lubricating structure, and designs the running clearance of 0.35-0.402mm and take surface through cure process measure.
4. AP1000 nuclear power technology according to claim 1 is derived pump with normal waste heat, it is characterized in that: described delivery chamber (5) and delivery chamber cover plate (2) adopt forging molding, the moulding of numerical control machining center time processing.
5. AP1000 nuclear power technology according to claim 1 is derived pump with normal waste heat, it is characterized in that: described pump shaft (8) is upper is provided with throat's lining by key; Throat's lining (7) is designed to maze-type structure, between pump shaft and throat's lining, some throttle clearance is set, and makes fluid head decline and reduces fluid leakage, the mechanical seal parts in protection Seal cage through throttling repeatedly.
6. AP1000 nuclear power technology according to claim 1 is derived pump with normal waste heat, it is characterized in that: described coupling adopts extended type flexible membrane coupling, coupling is divided into pump end mounting disc (13), lengthens spacing shaft (14) and motor side mounting disc (15), the mounting disc of pump end, lengthen spacing shaft mounting disc is connected successively with motor side, the mounting disc of pump end is connected with pump shaft (8) by key, and motor side mounting disc is connected with motor output shaft (16) by key.
7. AP1000 nuclear power technology according to claim 6 is derived pump with normal waste heat, it is characterized in that: described bearing part comprises bearing housing (12), bearing (10) and bearing box (11), bearing adopts the angular contact ball bearing of a pair of face-to-face configuration, angular contact ball bearing is set with bearing box (11) outward, bearing (10) and bearing box (11) are arranged on bearing housing (12) inside, between bearing housing (12) and pump cover (6), support with middle linkage section (9), and bearing housing is connected with pump cover by bolt.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410079893.3A CN103821766A (en) | 2014-03-06 | 2014-03-06 | Normal afterheat guide-out pump for AP 1000 nuclear power technology |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410079893.3A CN103821766A (en) | 2014-03-06 | 2014-03-06 | Normal afterheat guide-out pump for AP 1000 nuclear power technology |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN103821766A true CN103821766A (en) | 2014-05-28 |
Family
ID=50756995
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201410079893.3A Pending CN103821766A (en) | 2014-03-06 | 2014-03-06 | Normal afterheat guide-out pump for AP 1000 nuclear power technology |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN103821766A (en) |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS55142995A (en) * | 1979-04-23 | 1980-11-07 | Hitachi Ltd | Static pressure bearing for vertical shaft pump |
| CN102562609A (en) * | 2012-02-15 | 2012-07-11 | 湖南湘电长沙水泵有限公司 | Nuclear three-stage waste heat discharge pump for AP1000 nuclear power station |
| CN203223417U (en) * | 2013-02-27 | 2013-10-02 | 江苏海狮泵业制造有限公司 | Novel residual heat removal pump |
| CN203717452U (en) * | 2014-03-06 | 2014-07-16 | 大连深蓝泵业有限公司 | Normal residual heat removal pump for AP 1000 nuclear power technology |
-
2014
- 2014-03-06 CN CN201410079893.3A patent/CN103821766A/en active Pending
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS55142995A (en) * | 1979-04-23 | 1980-11-07 | Hitachi Ltd | Static pressure bearing for vertical shaft pump |
| CN102562609A (en) * | 2012-02-15 | 2012-07-11 | 湖南湘电长沙水泵有限公司 | Nuclear three-stage waste heat discharge pump for AP1000 nuclear power station |
| CN203223417U (en) * | 2013-02-27 | 2013-10-02 | 江苏海狮泵业制造有限公司 | Novel residual heat removal pump |
| CN203717452U (en) * | 2014-03-06 | 2014-07-16 | 大连深蓝泵业有限公司 | Normal residual heat removal pump for AP 1000 nuclear power technology |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN103256246B (en) | Fluid-dynamic-pressure three-level mechanical sealing device for reactor coolant pump | |
| KR102193340B1 (en) | Primary circulating pump assembly | |
| CN201763613U (en) | High-pressure self-balance horizontal multistage centrifugal pump | |
| CN203717452U (en) | Normal residual heat removal pump for AP 1000 nuclear power technology | |
| CN201650786U (en) | Mechanical secondary steam circulating compressor | |
| CN101846028B (en) | Method for preventing hydroelectric generating set from being lifted | |
| CN201574979U (en) | Main circulation pump set for nuclear power plant | |
| CN205618420U (en) | Hua longyi is cooling water pump for nuclear power technology | |
| CN203743045U (en) | Normal residual heat removal pump for third-generation AP1000 (advanced passive pressurized water reactor 1000) nuclear power station | |
| CN203743013U (en) | Third-generation nuclear power AP1000 (advanced passive pressurized water reactor 1000) residual heat removal pump | |
| CN103821766A (en) | Normal afterheat guide-out pump for AP 1000 nuclear power technology | |
| CN203272221U (en) | Fluid dynamic pressure three-level mechanical sealing device of reactor coolant pump | |
| CN103821755A (en) | Normal afterheat discharging pump for third-generation AP1000 advanced pressurized water reactor nuclear power station | |
| CN201521433U (en) | Hydrostatic and hydrodynamic combined three-stage mechanical seal device for nuclear reactor coolant pump | |
| CN103821731A (en) | Afterheat discharging pump for third-generation nuclear power technology AP1000 | |
| CN210949153U (en) | Small-flow ultrahigh-pressure boiler feed pump | |
| CN203257723U (en) | Waste heat discharge pump | |
| CN205618370U (en) | Hua longyi is low pressure safe injection pump for nuclear power technology | |
| CN220081683U (en) | Low-pressure safety injection pump with double-suction impeller structure for first stage of pressurized water reactor nuclear power plant | |
| CN204610292U (en) | A kind of pipeline conveying centrifugal pump | |
| CN103511173A (en) | Water turbine provided with four servomotors on top cover | |
| CN220566280U (en) | Bearing box structure of multistage pump | |
| CN220600016U (en) | Large-scale hydrogenation feeding hydraulic turbine unit | |
| CN217926392U (en) | Deformation controllable and auxiliary supporting device of high-temperature and high-pressure pump | |
| CN209444578U (en) | A kind of non-maintaining submersible sewage pump of environmental protection |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C02 | Deemed withdrawal of patent application after publication (patent law 2001) | ||
| WD01 | Invention patent application deemed withdrawn after publication |
Application publication date: 20140528 |