CN104599730A - Pressurized water reactor (PWR) nuclear power generation mechanism - Google Patents
Pressurized water reactor (PWR) nuclear power generation mechanism Download PDFInfo
- Publication number
- CN104599730A CN104599730A CN201410819893.2A CN201410819893A CN104599730A CN 104599730 A CN104599730 A CN 104599730A CN 201410819893 A CN201410819893 A CN 201410819893A CN 104599730 A CN104599730 A CN 104599730A
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- China
- Prior art keywords
- steam
- pipeline
- pressure cylinder
- water
- reactor
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Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
- G21D5/04—Reactor and engine not structurally combined
- G21D5/08—Reactor and engine not structurally combined with engine working medium heated in a heat exchanger by the reactor coolant
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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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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention provides a pressurized water reactor (PWR) nuclear power generation mechanism, and belongs to the technical field of generation equipment. The PWR nuclear power generation mechanism is that a reactor is arranged in a safety housing; the safety housing is connected with a light water pipeline; a pressure stabilizing tank is arranged on the light water pipeline; the light water pipeline is connected to a heat exchanger chamber of a steam generator, and water flows through a light water circulating pump and then returns in to the safety housing along the light water pipeline; a steam pipeline which is connected with a steam turbine is connected to the upper part of the steam generator; the steam turbine is in transmission connection with a generator; a low pressure cylinder of the steam turbine is connected to a condenser through the steam pipeline; the condenser is connected with a condense water pump through a condensing pipeline; the condense water pump is sequentially connected with a low-temperature preheater, a preheating circulating pump and a high-temperature preheater through preheating pipelines, and stream reflows into a steam cavity of the steam generator. The PWR nuclear power generation mechanism is high in power density, compact in structure, safe, easily controlled, and low in construction cost and generation cost.
Description
Technical field
The present invention relates to 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 can utilize natural uranium most effectively.Because deuterium oxide moderated performance is good, absorb neutron few, this not only can make fuel by direct natural uranium, and fuel burns more saturating.The amount that heavy water reactor consumes natural uranium than light water reactor is few, if adopt low concentration uranium, can save natural uranium 38%.In various thermal-neutron reactor, the natural uranium amount that heavy water reactor needs is minimum.In addition, heavy water reactor, to the strong adaptability of fuel, can use another kind of nuclear fuel instead easily.Its major defect is, 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 invention solves the deficiencies in the prior art, provides a kind of compressed water reactor nuclear power power facility.
Technical scheme of the present invention realizes in the following manner, this compressed water reactor nuclear power power facility, its structure comprises containment, reactor, steam generator and generator, reactor is provided with in containment, containment connects light-water pipeline, light-water pipeline is provided with buffer tank, is back in containment along light-water pipeline after light-water ebullator after light-water pipeline is connected to the heat exchanging chamber of steam generator; Steam generator top is established and is connected with steam pipework, steam pipework connects steam turbine high-pressure cylinder, steam turbine high-pressure cylinder is in transmission connection turbine low pressure cylinder, steam-water separator is provided with between steam turbine high-pressure cylinder and turbine low pressure cylinder, turbine low pressure cylinder is in transmission connection generator, turbine low pressure cylinder is connected on condenser through steam pipework, condenser connects condensate pump by condenser pipe, and condensate pump connects by preheating pipeline the 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, cooling medium pipeline is provided with cooling medium ebullator.
Buffer tank bottom is provided with standby electric heater, and top is provided with emergent cooling sprayer.
Reactor is provided with control rod.
The beneficial effect that the present invention is compared with prior art produced 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 low, its buffer tank is when nuclear power is checked bust and raises suddenly again, carry out regulating action by emergent cooling sprayer or standby electric heater for corresponding situation, control to export vapor pressure, ensure that light-water pipeline normally runs.Many control rods composition cluster types, be used for controlling the speed of reactor nuclear reaction.If reactor breaks down, immediately abundant control rod is inserted reactor core, within very short time, reactor will quit work, and this guarantees the safety of reactor operation.
This compressed water reactor nuclear power power facility is reasonable in design, structure is simple, safe and reliable, easy to use, be easy to safeguard, have good value for applications.
Accompanying drawing explanation
Accompanying drawing 1 is structural representation of the present invention.
Mark in accompanying drawing represents respectively:
1, containment, 2, reactor, 3, light-water pipeline, 4, buffer tank, 5, steam generator, 6, heat exchanging chamber, 7, 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, preheating pipeline, 17, low-temperature pre-heater, 18, warm-up cycle pump, 19, high-temperature preheater, 20, vapor chamber, 21, cooling medium is around pipe, 22, cooling medium pipeline, 23, cooling medium ebullator, 24, standby 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 invention is described in detail below.
As shown in drawings, compressed water reactor nuclear power power facility of the present invention, its structure comprises containment 1, reactor 2, steam generator 5 and generator 12, reactor 2 is provided with in containment 1, containment 1 connects light-water pipeline 3, light-water pipeline 3 is provided with buffer tank 4, is back in containment 1 along light-water pipeline after light-water ebullator 7 after light-water pipeline 3 is connected to the heat exchanging chamber 6 of steam generator 5, steam generator 5 top is established and is connected with steam pipework 8, steam pipework 8 connects steam turbine high-pressure cylinder 9, steam turbine high-pressure cylinder 9 is in transmission connection turbine low pressure cylinder 10, steam-water separator 11 is provided with between steam turbine high-pressure cylinder 9 and turbine low pressure cylinder 10, turbine low pressure cylinder 10 is in transmission connection generator 12, 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, cooling medium pipeline 22 is provided with cooling medium ebullator 23.Buffer tank 4 bottom is provided with standby electric heater 24, and top is provided with emergent cooling sprayer 25.Reactor 2 is provided with control rod 26.This compressed water reactor nuclear power power facility is reasonable in design, structure is simple, 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, reactor is provided with in containment, containment connects light-water pipeline, light-water pipeline is provided with buffer tank, is back in containment along light-water pipeline after light-water ebullator after light-water pipeline is connected to the heat exchanging chamber of steam generator; Steam generator top is established and is connected with steam pipework, steam pipework connects steam turbine high-pressure cylinder, steam turbine high-pressure cylinder is in transmission connection turbine low pressure cylinder, steam-water separator is provided with between steam turbine high-pressure cylinder and turbine low pressure cylinder, turbine low pressure cylinder is in transmission connection generator, turbine low pressure cylinder is connected on condenser through steam pipework, condenser connects condensate pump by condenser pipe, and condensate pump connects by preheating pipeline the 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, cooling medium pipeline is provided with cooling medium ebullator.
2. compressed water reactor nuclear power power facility according to claim 1, it is characterized in that buffer tank bottom is provided with standby electric heater, top is provided with emergent cooling sprayer.
3. compressed water reactor nuclear power power facility according to claim 1, is characterized in that reactor is provided with control rod.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410819893.2A CN104599730A (en) | 2014-12-25 | 2014-12-25 | Pressurized water reactor (PWR) nuclear power generation mechanism |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410819893.2A CN104599730A (en) | 2014-12-25 | 2014-12-25 | Pressurized water reactor (PWR) nuclear power generation mechanism |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN104599730A true CN104599730A (en) | 2015-05-06 |
Family
ID=53125445
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201410819893.2A Pending CN104599730A (en) | 2014-12-25 | 2014-12-25 | Pressurized water reactor (PWR) nuclear power generation mechanism |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN104599730A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106050419A (en) * | 2016-06-23 | 2016-10-26 | 章礼道 | Combustion gas turbine and pressurized water reactor steam turbine combined circulation system |
| CN106194431A (en) * | 2016-06-23 | 2016-12-07 | 章礼道 | Gas turbine presurized water reactor steam turbine combined cycle without separator |
| CN106531247A (en) * | 2016-12-23 | 2017-03-22 | 中国核动力研究设计院 | Spraying type condensation device and reactor simulation test device secondary circuit system formed by same |
-
2014
- 2014-12-25 CN CN201410819893.2A patent/CN104599730A/en active Pending
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106050419A (en) * | 2016-06-23 | 2016-10-26 | 章礼道 | Combustion gas turbine and pressurized water reactor steam turbine combined circulation system |
| CN106194431A (en) * | 2016-06-23 | 2016-12-07 | 章礼道 | Gas turbine presurized water reactor steam turbine combined cycle without separator |
| CN106050419B (en) * | 2016-06-23 | 2018-08-14 | 章礼道 | Gas turbine presurized water reactor steam turbine combined cycle system |
| US10378389B2 (en) | 2016-06-23 | 2019-08-13 | Lidao ZHANG | Gas turbine and pressurized water reactor steam turbine combined circulation system |
| CN106531247A (en) * | 2016-12-23 | 2017-03-22 | 中国核动力研究设计院 | Spraying type condensation device and reactor simulation test device secondary circuit system formed by same |
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Legal Events
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| C06 | Publication | ||
| PB01 | Publication | ||
| WD01 | Invention patent application deemed withdrawn after publication | ||
| WD01 | Invention patent application deemed withdrawn after publication |
Application publication date: 20150506 |