CN202930058U - PWR (Pressurized Water Reactor ) nuclear power generating mechanism - Google Patents
PWR (Pressurized Water Reactor ) nuclear power generating mechanism Download PDFInfo
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- CN202930058U CN202930058U CN2012204864837U CN201220486483U CN202930058U CN 202930058 U CN202930058 U CN 202930058U CN 2012204864837 U CN2012204864837 U CN 2012204864837U CN 201220486483 U CN201220486483 U CN 201220486483U CN 202930058 U CN202930058 U CN 202930058U
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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Abstract
The utility model provides a PWR nuclear power generating mechanism, belonging to the technical field of generating equipment. A reactor is arranged in a containment vessel, the containment vessel is connected with a light-water pipeline, and the light-water pipeline equipped with a pressure stabilizing tank is connected with a heat exchange chamber of a steam generator, passes through a light-water circulating pump and then backflows into the containment vessel; and a steam pipeline is connected to the upper of the steam generator, and also connected with a steam turbine, the steam turbine is in transmission connection with a generator, a low pressure cylinder of the steam turbine is connected to a condenser via the steam pipeline, the condenser is connected with a coagulation water pump via a condensation pipeline, and the condensation pump is successively connected with a low-temperature preheater, a preheating circulation pump and a high-temperature preheater and backflows to a steam chamber of the steam generator via a preheating pipeline. The PWR nuclear power generating mechanism has the advantages of high power density, compact structure, safe and easy control, and low production and power generation cost.
Description
Technical field
The utility model relates to the generating set technical field, specifically a kind of compressed water reactor nuclear power power facility.
Background technology
General, the outstanding advantages of heavy water reactor is to utilize most effectively natural uranium.Because the heavy water slowing properties is good, absorb neutron few, this not only can directly make fuel with natural uranium, and fuel burns more thoroughly.Heavy water reactor is lacked than the amount that light water reactor consumes natural uranium, if adopt low concentration uranium, can save natural uranium 38%.In various thermal-neutron reactors, the natural uranium amount that heavy water reactor needs is minimum.In addition, the strong adaptability of heavy water reactor to fuel can be used another kind of nuclear fuel at an easy rate instead.Its major defect is that the volume ratio light water reactor is large.Expenditure of construction is high, and heavy water is expensive, and cost of electricity-generating is also higher.
Summary of the invention
Technical assignment of the present utility model is to solve the deficiencies in the prior art, and a kind of compressed water reactor nuclear power power facility is provided.
The technical solution of the utility model realizes in the following manner, this compressed water reactor nuclear power power facility, its structure comprises containment, reactor, steam generator and generator, be provided with reactor in containment, containment connects the light-water pipeline, be provided with buffer tank on the light-water pipeline, the heat exchanging chamber that the light-water pipeline is connected to steam generator is back in containment along the light-water pipeline after by the light-water ebullator; Steam generator top is established and is connected with steam pipework, steam pipework connects steam turbine high-pressure cylinder, the steam turbine high-pressure cylinder turbine low pressure cylinder that is in transmission connection, be provided with steam-water separator between steam turbine high-pressure cylinder and turbine low pressure cylinder, the turbine low pressure cylinder generator that is in transmission connection, turbine low pressure cylinder is connected on condenser through steam pipework, condenser connects condensate pump by condenser pipe, and condensate pump connects by the preheating pipeline vapor chamber that low-temperature pre-heater, warm-up cycle pump and high-temperature preheater are back to steam generator successively; Be provided with cooling medium in condenser around pipe, cooling medium is connected with the cooling medium pipeline of condenser outside around pipe, is provided with the cooling medium ebullator on the cooling medium pipeline.
The buffer tank bottom is provided with the reserve electric heater, and top is provided with emergent cooling sprayer.
Be provided with control rod on reactor.
The beneficial effect that the utility model compared with prior art produces is:
This compressed water reactor nuclear power power facility power density is high, compact conformation, safety is control easily, cost and cost of electricity-generating are low, its buffer tank nuclear power is again checked bust and when raising suddenly, for the regulating action of carrying out of corresponding situation, control the output vapor pressure by emergent cooling sprayer or reserve electric heater, guarantee that the light-water pipeline normally moves.Many control rods are formed the cluster type, be used for controlling the speed of reactor nuclear reaction.If reactor breaks down, immediately abundant control rod is inserted reactor core, very short time the internal reaction heap will quit work, this has just guaranteed the safety of reactor operation.
This compressed water reactor nuclear power power facility is reasonable in design, simple in structure, safe and reliable, easy to use, be easy to safeguard, has good value for applications.
Description of drawings
Accompanying drawing 1 is structural representation of the present utility model.
Mark in accompanying drawing represents respectively:
1, containment, 2, reactor, 3, the light-water pipeline, 4, buffer tank, 5, steam generator, 6, heat exchanging chamber, 7, the light-water ebullator, 8, steam pipework, 9, steam turbine high-pressure cylinder, 10, turbine low pressure cylinder, 11, steam-water separator, 12, generator, 13, condenser, 14, condenser pipe, 15, condensate pump, 16, the preheating pipeline, 17, low-temperature pre-heater, 18, the warm-up cycle pump, 19, high-temperature preheater, 20, vapor chamber, 21, cooling medium is around pipe, 22, the cooling medium pipeline, 23, the cooling medium ebullator, 24, the reserve electric heater, 25, emergent cooling sprayer, 26, control rod.
Embodiment
Below in conjunction with accompanying drawing, compressed water reactor nuclear power power facility of the present utility model is described in detail below.
as shown in drawings, compressed water reactor nuclear power power facility of the present utility model, its structure comprises containment 1, reactor 2, steam generator 5 and generator 12, be provided with reactor 2 in containment 1, containment 1 connects light-water pipeline 3, be provided with buffer tank 4 on light-water pipeline 3, the heat exchanging chamber 6 that light-water pipeline 3 is connected to steam generator 5 is back in containment 1 along the light-water pipeline by light-water ebullator 7 is rear, steam generator 5 tops are established and are connected with steam pipework 8, steam pipework 8 connects steam turbine high-pressure cylinder 9, steam turbine high-pressure cylinder 9 turbine low pressure cylinder 10 that is in transmission connection, be provided with steam-water separator 11 between steam turbine high-pressure cylinder 9 and turbine low pressure cylinder 10, turbine low pressure cylinder 10 generator 12 that is in transmission connection, turbine low pressure cylinder 10 is connected on condenser 13 through steam pipework 8, condenser 13 connects condensate pump 15 by condenser pipe 14, condensate pump 15 connects low-temperature pre-heater 17 successively by preheating pipeline 16, warm-up cycle pump 18 and high-temperature preheater 19 are back to the vapor chamber 20 of steam generator 5, be provided with cooling medium in condenser 13 around pipe 21, cooling medium is connected with the cooling medium pipeline 22 of condenser outside around pipe 21, is provided with cooling medium ebullator 23 on cooling medium pipeline 22.Buffer tank 4 bottoms are provided with reserve electric heater 24, and top is provided with emergent cooling sprayer 25.Be provided with control rod 26 on reactor 2.This compressed water reactor nuclear power power facility is reasonable in design, simple in structure, safe and reliable, easy to use, be easy to safeguard.
Claims (3)
1. compressed water reactor nuclear power power facility, it is characterized in that comprising containment, reactor, steam generator and generator, be provided with reactor in containment, containment connects the light-water pipeline, be provided with buffer tank on the light-water pipeline, the heat exchanging chamber that the light-water pipeline is connected to steam generator is back in containment along the light-water pipeline after by the light-water ebullator; Steam generator top is established and is connected with steam pipework, steam pipework connects steam turbine high-pressure cylinder, the steam turbine high-pressure cylinder turbine low pressure cylinder that is in transmission connection, be provided with steam-water separator between steam turbine high-pressure cylinder and turbine low pressure cylinder, the turbine low pressure cylinder generator that is in transmission connection, turbine low pressure cylinder is connected on condenser through steam pipework, condenser connects condensate pump by condenser pipe, and condensate pump connects by the preheating pipeline vapor chamber that low-temperature pre-heater, warm-up cycle pump and high-temperature preheater are back to steam generator successively; Be provided with cooling medium in condenser around pipe, cooling medium is connected with the cooling medium pipeline of condenser outside around pipe, is provided with the cooling medium ebullator on the cooling medium pipeline.
2. compressed water reactor nuclear power power facility according to claim 1 is characterized in that the buffer tank bottom is provided with the reserve electric heater, and top is provided with emergent cooling sprayer.
3. compressed water reactor nuclear power power facility according to claim 1, is characterized in that being provided with on reactor control rod.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012204864837U CN202930058U (en) | 2012-09-23 | 2012-09-23 | PWR (Pressurized Water Reactor ) nuclear power generating mechanism |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012204864837U CN202930058U (en) | 2012-09-23 | 2012-09-23 | PWR (Pressurized Water Reactor ) nuclear power generating mechanism |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN202930058U true CN202930058U (en) | 2013-05-08 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2012204864837U Expired - Fee Related CN202930058U (en) | 2012-09-23 | 2012-09-23 | PWR (Pressurized Water Reactor ) nuclear power generating mechanism |
Country Status (1)
| Country | Link |
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| CN (1) | CN202930058U (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104484528A (en) * | 2014-12-18 | 2015-04-01 | 国家电网公司 | Nuclear power unit power and electric hybrid simulation platform based on PSCAD |
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2012
- 2012-09-23 CN CN2012204864837U patent/CN202930058U/en not_active Expired - Fee Related
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104484528A (en) * | 2014-12-18 | 2015-04-01 | 国家电网公司 | Nuclear power unit power and electric hybrid simulation platform based on PSCAD |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| C17 | Cessation of patent right | ||
| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20130508 Termination date: 20130923 |