CN201991617U - Circulating power generation system of pressurized water reactor nuclear power gas turbine - Google Patents
Circulating power generation system of pressurized water reactor nuclear power gas turbine Download PDFInfo
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- CN201991617U CN201991617U CN2011200098177U CN201120009817U CN201991617U CN 201991617 U CN201991617 U CN 201991617U CN 2011200098177 U CN2011200098177 U CN 2011200098177U CN 201120009817 U CN201120009817 U CN 201120009817U CN 201991617 U CN201991617 U CN 201991617U
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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
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Abstract
The utility model discloses a circulating power generation system of a pressurized water reactor nuclear power gas turbine, which comprises a pressurized water reactor nuclear reaction system, a power generator, a controlling device, a steam generator, a three-stage gas turbine for driving the power generator, a three-stage compressor, a three-stage heat exchanger, a two-stage intercooler, a low-temperature heat exchanger and a cooling tower which form through pipelines a first loop system, a second loop system with water as a heat-conducting working medium, a third loop system with helium as a heat-conducting working medium and for driving the three-stage gas turbine and three cooling loop systems. The circulating power generation system of the pressurized water reactor nuclear power gas turbine is small in volume, reliable, high in power generation efficiency, free of carbon dioxide and pollution, and is carbon-free power generation technology.
Description
Technical field
The utility model relates to power generation system, especially a kind of pressurized water reactor nuclear-powered gas turbine cycle generating system.
Background technique
Present gas turbine is to be energy source with the fuel oil basically, and volume is big, and power is limited, and reliability is not high.And waste the non-renewable energy, contaminated air.
The model utility content
The purpose of this utility model is: a kind of pressurized water reactor nuclear-powered gas turbine cycle generating system is provided, and volume is little, good reliability, and the generating efficiency height does not have CO
2Greenhouse gases produce, not contaminated air.
For achieving the above object, the utility model can be taked following technical proposals:
A kind of pressurized water reactor nuclear-powered gas turbine of the utility model cycle generating system, comprise the pressurized water reactor nuclear reaction system, generator, and control gear, also comprise steam generator, be used to drive three grades of gas turbines of described generator, three stage compressor, three grades of heat exchangers, the secondary intercooler, cryogenic heat exchanger, and cooling tower
The water outlet of the high pressure heating water chamber of described pressurized water reactor nuclear reaction system is communicated with the U type tube inlet of described steam generator bottom by the pipeline that has voltage stabilizer, the outlet of described U type pipe is communicated with the backwater mouth of described high pressure heating water chamber by the pipeline that has main pump, constitutes first circuit system;
The hot steam outlet of described steam generator is communicated with first inlet of described three grades of heat exchangers respectively by pipeline, first outlet of three grades of heat exchangers is communicated with the backwater mouth of described steam generator by pipeline respectively, constitutes second circuit system of being done heat-transfer working medium by water;
Third level compressor outlet in the described three stage compressor is communicated with second inlet of regenerator by pipeline, second of first order heat exchanger in second outlet of regenerator and the described three grades of heat exchangers enters the mouth and to be communicated with, second outlet of first order heat exchanger is communicated with the inlet of first order gas turbine in described three grades of gas turbines, second inlet of the outlet second level heat exchanger of first order gas turbine is communicated with, second outlet of second level heat exchanger is communicated with the inlet of second level gas turbine, second inlet of the outlet third level heat exchanger of second level gas turbine is communicated with, second outlet of third level heat exchanger is communicated with first inlet of regenerator, first outlet of regenerator is communicated with second inlet of cryogenic heat exchanger, second outlet of cryogenic heat exchanger is communicated with the inlet of described first order compressor, first inlet of the first order intercooler in the outlet of first order compressor and the described secondary intercooler is communicated with, first outlet of first order intercooler is communicated with the inlet of high stage compressor, the outlet of high stage compressor is communicated with first inlet of second level intercooler, first outlet of second level intercooler is communicated with the inlet of third level compressor, constitutes and does heat-transfer working medium by helium, and be used to drive the tertiary circuit system of three grades of gas turbines;
First, second, third outlet of described cooling tower is communicated with first inlet of cryogenic heat exchanger, second inlet of first order intercooler, second inlet of second level intercooler respectively, first, second, third inlet of cooling tower is communicated with first outlet of cryogenic heat exchanger, second outlet of first order intercooler, second outlet of second level intercooler respectively, constitutes three cooling circuit systems respectively.
Described three stage compressor is Axial Flow Compressor.
Compared with prior art the beneficial effects of the utility model are:
The utility model pressurized water reactor nuclear-powered gas turbine cycle generating system, by the pressurized water reactor nuclear reaction system, heat absorption and thermal energy transfer system (constituting) by described steam generator, three grades of gas turbines, three stage compressor, three grades of heat exchangers, secondary intercooler, cryogenic heat exchanger and cooling towers, power generation system three parts are formed, the pressurized water reactor nuclear reaction system is converted into nuclear energy the high temperature heat of working fluid, heat absorption becomes the High Temperature High Pressure helium with the thermal energy transfer system with steam heat, the propelling gas turbine engine generating.The whole system volume is little, good reliability, and the generating efficiency height does not have CO
2Greenhouse gases produce, and contaminated air is not a kind of carbon-free generation technology.
Description of drawings
Fig. 1 is the structural representation of the utility model pressurized water reactor nuclear-powered gas turbine cycle generating system.
Fig. 2 is that the utility model embodiment works in constant temperature thermal source T
1And T
0Between irreversible enclosed in three grades of gas turbine cycle models of cold time reheat heat schematic representation.
Embodiment
As shown in Figure 1, a kind of pressurized water reactor nuclear-powered gas turbine of the utility model cycle generating system, comprise pressurized water reactor nuclear reaction system S, generator D, and control gear, also comprise steam generator V, be used to drive three grades of gas turbines (first order gas turbine TU1 of described generator D, second level gas turbine TU2 and third level gas turbine TU3), three grades of Axial Flow Compressor (first order Axial Flow Compressor C1, second level Axial Flow Compressor C2 and third level Axial Flow Compressor C3), three grades of heat exchanger (first order heat exchanger R5, second level heat exchanger R6 and third level heat exchanger R7), secondary intercooler (first order intercooler R1 and second level intercooler R2), cryogenic heat exchanger R3 and cooling tower C;
The water outlet of the high pressure heating water chamber of described pressurized water reactor nuclear reaction system S is communicated with the U type tube inlet of described steam generator V bottom by the pipeline that has voltage stabilizer P, the outlet of described U type pipe is communicated with the backwater mouth of described high pressure heating water chamber by the pipeline that has main pump P1, constitutes first circuit system.In first circuit system, behind the heat release of high pressure water absorption pressure water-water reactor nuclear reaction system S fuel element, enter in the U type pipe of steam generator V bottom, heat is passed to the water of second circuit system;
The hot steam outlet of described steam generator V is communicated with first inlet of described three grades of heat exchanger R5, R6 and R7 respectively by pipeline, first outlet of three grades of heat exchangers (first order heat exchanger R5, second level heat exchanger R6 and third level heat exchanger R7) is communicated with by the backwater mouth of pipeline with described steam generator V respectively, constitutes second circuit system of being done heat-transfer working medium by water.The water of second circuit system is in the U type pipe outer flow mistake of steam generator V bottom, seethe with excitement after absorbing the heat of first circuit system, the steam that produces flows out from the hot steam outlet on steam generator V top, and heat is passed to helium in three grades of heat exchangers of tertiary circuit system (first order heat exchanger R5, second level heat exchanger R6 and third level heat exchanger R7);
Described three grades of Axial Flow Compressors (first order Axial Flow Compressor C1, second level Axial Flow Compressor C2 and third level Axial Flow Compressor C3) in third level Axial Flow Compressor C3 outlet enter the mouth with second of regenerator R4 by pipeline and be communicated with, second of first order heat exchanger R5 in second outlet of regenerator R4 and the described three grades of heat exchangers enters the mouth and to be communicated with, second outlet and described three grades of gas turbines (first order gas turbine TU1 of first order heat exchanger R5, second level gas turbine TU2 and third level gas turbine TU3) in the inlet of first order gas turbine TU1 be communicated with, second inlet of the outlet second level heat exchanger R6 of first order gas turbine TU1 is communicated with, second outlet of second level heat exchanger R6 is communicated with the inlet of second level gas turbine TU2, second inlet of the outlet third level heat exchanger R7 of second level gas turbine TU2 is communicated with, second outlet of third level heat exchanger R7 is communicated with first inlet of regenerator R4, first outlet of regenerator R4 is communicated with second inlet of cryogenic heat exchanger R3, second outlet of cryogenic heat exchanger R3 is communicated with the inlet of described first order Axial Flow Compressor C1, the outlet of first order Axial Flow Compressor C1 and described secondary intercooler R1, first inlet of first order intercooler R1 among the R2 is communicated with, first outlet of first order intercooler R1 is communicated with the inlet of second level Axial Flow Compressor C2, the outlet of second level Axial Flow Compressor C2 is communicated with first inlet of second level intercooler R2, first outlet of second level intercooler R2 is communicated with the inlet of third level Axial Flow Compressor C3, constitutes and does heat-transfer working medium by helium, and be used to drive three grades of gas turbines (first order gas turbine TU1, second level gas turbine TU2 and third level gas turbine TU3) the tertiary circuit system.Helium in the tertiary circuit system absorbs heat and becomes high temperature and high pressure gas in described three grades of heat exchangers, expansion working in described gas turbine drives described gas turbine, the described generator D generating of gas turbine drives;
First, second, third outlet of described cooling tower C is communicated with first inlet of cryogenic heat exchanger R3, second inlet of first order intercooler R1, second inlet of second level intercooler R2 respectively, first, second, third inlet of cooling tower C is communicated with first outlet of cryogenic heat exchanger R3, second outlet of first order intercooler R1, second outlet of second level intercooler R2 respectively, constitutes three cooling circuit systems respectively.
Figure 2 shows that and work in constant temperature thermal source T
1And T
0Between irreversible enclosed in the tephigram of three grades of gas turbine cycle of cold time reheat heat.Described backheat is pined in the cold circulation again, gas was heated by second level heat exchanger again after heat was meant first order turbo machine expansion working again, backheat is meant that the gas that gas and high stage compressor come out behind the turbo machine expansion working of the second level carries out heat exchange, in cold being meant after gas that first order compressor comes out is by water quench enter high stage compressor.Wherein: T is a temperature, and S is the thermodynamic entropy of working medium, is irreversible constant temperature source brayton cycle l-2-3-4-5-6-7-8-9-10-11-12-13-14-l.L-2 is that (pressure ratio is the irreversible adiabatic compression process of gas in low pressure compressor
, the ratio of colding pressing in also claiming); 2-3 is the cooling procedure of gas in intercooler; 3--4 is that (pressure ratio is the irreversible adiabatic compression process of gas in intermediate pressure compressor
, pressure ratio is identical); 5-6 is that (pressure ratio is the irreversible adiabatic compression process of gas in high-pressure compressor
,
Being overall pressure tatio) 6-7 is the warm of gas in regenerator; 7-8 is that working medium is from first order heat exchanger R5 endothermic process; 8-9 is the irreversible adiabatic expansion process of working medium in first order turbine; 9-10 be working medium from second level heat exchanger R6 endothermic process, 10-11 is the irreversible adiabatic expansion process of working medium in the turbine of the second level; 11-12 be working medium from third level heat exchanger R7 endothermic process, 12-13 is the irreversible adiabatic expansion process of working medium in third level turbine; 13-14 are the exothermic process of exhaust in regenerator; 14 1 l are the exothermic process of exhaust to low-temperature heat source.1--2 s, 3-4 s and 6-7 s are l one 2,3-4 and 6-7 corresponding reversible adiabatic compression and inflation processes.Gas compressor internal loss internal efficiency
(efficient of establishing high-pressure compressor and low pressure compressor is identical), the internal loss internal efficiency of turbo machine
Represent promptly have:
If working medium is the perfect gas of constant specific heat, its thermal capacity is C
WfThe thermal conductivity U of heat exchanger R5 between working medium and high low-temperature heat source
H2, heat exchanger R6, R7 thermal conductivity U
H1, regenerator R3 thermal conductivity U
L1, heat exchanger is reverse-flow, and thermal conductivity is that heat-transfer coefficient and heat transfer area are long-pending.By the heat transfer between working medium character, thermal source and working medium and the suction as can be known of heat exchanger theory, rate of heat release, backheat rate of heat flow and in cold heat exchange rate of heat flow be respectively:
Wherein
-
,
,
,
,
,
,
, each operating point temperature in the difference representative graph 2;
In the formula, E
H, E
L, E
1Be respectively the validity of high low-temperature side heat exchanger R5, R6, R7, regenerator R3 and intercooler R4,
E
H=l-exp(-NN)，E
L=l-exp(-NL)，
E
R=NR／(NR+1)，E
1=l-exp(-N1)
Wherein, N
i(R I) is number of transfer units, Ni=Ui/CWf for i=H, L.Circulation output power and efficient are:
P=Q
1+Q
2+Q
3-Q
4-Q
6-Q
7，
=P／(Q
1+Q
2+Q
3)
Claims (2)
1. pressurized water reactor nuclear-powered gas turbine cycle generating system, comprise pressurized water reactor nuclear reaction system (S), generator (D), and control gear, it is characterized in that: also comprise steam generator (V), be used to drive three grades of gas turbines (TU1, TU2 and TU3) of described generator (D), three stage compressor (C1, C2 and C3), three grades of heat exchangers (R5, R6 and R7), secondary intercooler (R1 and R2), cryogenic heat exchanger (R3), and cooling tower (C)
The water outlet of the high pressure heating water chamber of described pressurized water reactor nuclear reaction system (S) is communicated with the U type tube inlet of described steam generator (V) bottom by the pipeline that has voltage stabilizer (P), the outlet of described U type pipe is communicated with the backwater mouth of described high pressure heating water chamber by the pipeline that has main pump (P1), constitutes first circuit system;
The hot steam outlet of described steam generator (V) is communicated with first inlet of described three grades of heat exchangers (R5, R6 and R7) respectively by pipeline, first outlet of three grades of heat exchangers (R5, R6 and R7) is communicated with by the backwater mouth of pipeline with described steam generator (V) respectively, constitutes second circuit system of being done heat-transfer working medium by water;
Described three stage compressor (C1, C2 and C3) in third level compressor (C3) outlet enter the mouth with second of regenerator (R4) by pipeline and be communicated with, second outlet and described three grades of heat exchanger (R5 of regenerator (R4), R6 and R7) in second inlet of first order heat exchanger (R5) be communicated with, second outlet and described three grades of gas turbine (TU1 of first order heat exchanger (R5), TU2 and TU3) in the inlet of first order gas turbine (TU1) be communicated with, second inlet of the outlet second level heat exchanger (R6) of first order gas turbine (TU1) is communicated with, second outlet of second level heat exchanger (R6) is communicated with the inlet of second level gas turbine (TU2), second inlet of the outlet third level heat exchanger (R7) of second level gas turbine (TU2) is communicated with, second outlet of third level heat exchanger (R7) is communicated with first inlet of regenerator (R4), first outlet of regenerator (R4) is communicated with second inlet of cryogenic heat exchanger (R3), second outlet of cryogenic heat exchanger (R3) is communicated with the inlet of described first order compressor (C1), the outlet of first order compressor (C1) and described secondary intercooler (R1, first inlet of the first order intercooler (R1) R2) is communicated with, first outlet of first order intercooler (R1) is communicated with the inlet of high stage compressor (C2), the outlet of high stage compressor (C2) is communicated with first inlet of second level intercooler (R2), first outlet of second level intercooler (R2) is communicated with the inlet of third level compressor (C3), constitutes and does heat-transfer working medium by helium, and be used to drive three grades of gas turbine (TU1, TU2 and TU3) the tertiary circuit system;
First, second, third outlet of described cooling tower (C) is communicated with first inlet of cryogenic heat exchanger (R3), second inlet of first order intercooler (R1), second inlet of second level intercooler (R2) respectively, first, second, third inlet of cooling tower (C) is communicated with first outlet of cryogenic heat exchanger (R3), second outlet of first order intercooler (R1), second outlet of second level intercooler (R2) respectively, constitutes three cooling circuit systems respectively.
2. pressurized water reactor nuclear-powered gas turbine cycle generating system according to claim 1 is characterized in that: described three stage compressor (C1, C2 and C3) is Axial Flow Compressor.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2011200098177U CN201991617U (en) | 2011-01-13 | 2011-01-13 | Circulating power generation system of pressurized water reactor nuclear power gas turbine |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2011200098177U CN201991617U (en) | 2011-01-13 | 2011-01-13 | Circulating power generation system of pressurized water reactor nuclear power gas turbine |
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| Publication Number | Publication Date |
|---|---|
| CN201991617U true CN201991617U (en) | 2011-09-28 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2011200098177U Expired - Fee Related CN201991617U (en) | 2011-01-13 | 2011-01-13 | Circulating power generation system of pressurized water reactor nuclear power gas turbine |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102162397A (en) * | 2011-01-13 | 2011-08-24 | 绍兴文理学院 | Cycling generating system of pressurized water reactor nuclear power gas turbine |
| CN114856812A (en) * | 2022-05-13 | 2022-08-05 | 哈尔滨工程大学 | Closed type miniature gas turbine power system |
-
2011
- 2011-01-13 CN CN2011200098177U patent/CN201991617U/en not_active Expired - Fee Related
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102162397A (en) * | 2011-01-13 | 2011-08-24 | 绍兴文理学院 | Cycling generating system of pressurized water reactor nuclear power gas turbine |
| CN114856812A (en) * | 2022-05-13 | 2022-08-05 | 哈尔滨工程大学 | Closed type miniature gas turbine power system |
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| 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: 20110928 Termination date: 20140113 |