CN103117101B - For the start and stop servicing unit of integral reactor and the cold start-up method of integral reactor - Google Patents

For the start and stop servicing unit of integral reactor and the cold start-up method of integral reactor Download PDF

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CN103117101B
CN103117101B CN201310020289.9A CN201310020289A CN103117101B CN 103117101 B CN103117101 B CN 103117101B CN 201310020289 A CN201310020289 A CN 201310020289A CN 103117101 B CN103117101 B CN 103117101B
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water
storage tank
water storage
reactor
valve
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CN103117101A (en
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夏庚磊
彭敏俊
杜雪
余大力
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Harbin Engineering University
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    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
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Abstract

The present invention is to provide a kind of for the start and stop servicing unit of integral reactor and the cold start-up method of integral reactor.Start the import of separation vessel be connected with the outlet conduit of once through steam generator, steam (vapor) outlet is connected with main steam line through steam valve, hydrophobic outlet is connected with water storage tank; The outlet at bottom of water storage tank is connected with water circulating pump, export a road pipeline is connected with condenser by water storage tank outlet shutoff valve, water storage tank level control valve and desuperheat dropping equipment; Water circulating pump is connected with once through steam generator import feedwater piping by circulating water flow control valve; Feed pump is connected with condenser and is connected with once through steam generator inlet pipeline by main feed valve, is connected with water storage tank by cold valves.The present invention can realize the increasing temperature and pressure of primary Ioops cooling medium in the process of reactor start-up; Effectively set up secondary circuit starting pressure and start flow, avoiding the appearance of flowing instability phenomenon, and effectively reclaiming working medium and heat, shortening start-up time.

Description

For the start and stop servicing unit of integral reactor and the cold start-up method of integral reactor
Technical field
What the present invention relates to is the start and stop servicing unit of integral reactor.The present invention also relates to a kind of cold start-up method of integral reactor of start and stop servicing unit of integral reactor.
Background technology
Due to the requirement that space is arranged, integrated nuclear reactor tends to the once through steam generator adopting compact efficient.Secondary circuit working medium is forced to flow through heating surface, by primary Ioops coolant heating, through preheating, evaporation, overheated and produce superheated vapor deliver to turbine system acting.It is simple that once through steam generator has structure, and maneuverability is good, the feature that heat consumption rate is low, is particularly suitable for the atomic marine plant needing frequent variable load operation.Once through steam generator inside is made up of a hundreds of parallel port, and the hydrodynamic property curve of each passage is different, there is violent phase transition process during operation in evaporation tube, is easy to the diphasic flow wild effect producing various ways.In order to ensure the safe and stable operation of once through steam generator, the minimum feedwater flow of once through steam generator must be ensured.
In pressurized-water reactor nuclear power plant Cold Start, first to realize the increasing temperature and pressure process of primary Ioops cooling medium.And the heating rate of primary Ioops system must be strict controlled in 30-40 DEG C/below h, pressure increase can not be too fast.In normal course of operation, the feedwater of once through steam generator is the subcooled water carrying out condenser, in reactor Cold Start, the cold feedwater of continual mistake can take away amount of heat, and the mechanical work depending merely on voltage stabilizer electrical heating power and main pump cannot complete the increasing temperature and pressure process of primary Ioops system.And start requirement for meeting, must ensure that secondary side feedwater is all heated to be superheated vapor, this will have the reactor capability corresponding with feedwater flow after reactor start-up will be asked to complete.How to realize the increasing temperature and pressure of primary Ioops cooling medium in start-up course, complete the startup of reactor, and secondary circuit feedwater is heated to be superheated vapor; How the two-phase mixture that in start-up course, once through steam generator outlet produces processes, and is all problem in the urgent need to address.
Summary of the invention
The object of this invention is to provide a kind of increasing temperature and pressure that can realize primary Ioops cooling medium in the process of integral reactor startup, avoid the appearance of flowing instability phenomenon, and effectively reclaim working medium and heat, shorten the start and stop servicing unit for integral reactor of reactor start-up time.The present invention also aims to the cold start-up method that a kind of integral reactor based on the start and stop servicing unit for integral reactor of the present invention is provided.
The object of the present invention is achieved like this:
Start and stop servicing unit for integral reactor of the present invention comprises startup separation vessel 15, water storage tank 16 and water circulating pump 17; The import starting separation vessel 15 is connected with the outlet conduit of once through steam generator 4, and the steam (vapor) outlet starting separation vessel 15 is connected with main steam line through steam valve 20, and the hydrophobic outlet starting separation vessel 15 is connected with water storage tank 16; The outlet at bottom of water storage tank 16 is connected with water circulating pump 17, and water storage tank 16 outlet has a road pipeline to be connected with condenser 22 by water storage tank outlet shutoff valve 25, water storage tank level control valve 26 and desuperheat dropping equipment 27; Water circulating pump 17 is connected with once through steam generator 4 import feedwater piping by circulating water flow control valve 18; Feed pump 23 is connected with condenser 22 and passes through main feed valve 24 and is connected with once through steam generator 4 inlet pipeline, is connected with water storage tank 16 by cold valves 28; Circulating water flow control valve 18 is connected with steam generator feed water control system with main feed valve 24; Water storage tank level control valve 26, steam valve 20 and cold valves 28 are connected with water storage tank control pressurer system.
Start and stop servicing unit for integral reactor of the present invention can also comprise:
1, water circulating pump 17 is exported and also has a road pipeline to be connected with water storage tank 16 by recirculation water flowrate control valve 19, and recirculation water flowrate control valve 19 is connected with steam generator feed water control system.
2, described startup separation vessel 15 is external steam-water separator, for vapour, gas-liquid two-phase liquid being separated in start-up course, after having started, by the switching of flowrate control valve 28 and flowrate control valve 29, startup separation vessel is exited secondary coolant circuit system.
3, described water circulating pump 17 is power-actuated water pump, and pump rotary speed opens at reactor, stop remaining constant in process, at once through steam generator 4, start between separation vessel 15 and water storage tank 16 and set up stable circulating water flow.
Cold start-up method based on the integral reactor of the start and stop servicing unit for integral reactor of the present invention comprises the following steps:
(1) after reactor water-filling has been vented, reactor has been in full water state, opens voltage stabilizer shower valve, uses the power of voltage stabilizer electric heating part 9 and the mechanical work of main pump 3 to improve primary Ioops coolant temperature;
(2) while primary Ioops system increasing temperature and pressure, start and stop backup system water storage tank control pressurer system action regulating tank pressure meets the demands, water circulating pump 17 is opened, recirculated water enters once through steam generator 4 by water storage tank 16 through circulating water flow control valve 18, flowed back to water storage tank 16 by after primary Ioops coolant heating, complete and once circulate;
(3) after voltage stabilizer 7 temperature meets the demands, set up voltage stabilizer 7 vapour chamber by letdown flow operation valve 11 draining, then utilize the power of voltage stabilizer electric heating part 9 to improve voltage stabilizer 7 pressure to rated operating pressures;
(4) adjust reactor power control system 12 realization response heap critical, promote reactor 1 power, realize core heat temperature raising, along with the raising of reactor capability, secondary circuit recirculated water produces boiling gradually;
(5) along with the lifting of reactor capability, steam generator feed water control system constantly adjusts the aperture of recirculation flow control valve 19, circulating water flow control valve 18 and main feed valve 24, ensures that once through steam generator import feedwater flow is stablized.
The invention provides a kind of start and stop backup system being equipped with the integral reactor of water circulating pump, the increasing temperature and pressure of primary Ioops cooling medium can be realized in the process that this system starts at integral reactor, complete the startup of reactor; Effectively set up secondary circuit starting pressure and start flow, avoiding the appearance of flowing instability phenomenon, and effectively reclaiming working medium and heat, shortening the reactor start-up time.
The invention has the beneficial effects as follows, achieve the increasing temperature and pressure of primary Ioops cooling medium and the safe and stable operation of once through steam generator in reactor Cold Start, most of working medium and heat can be reclaimed, use the mode of core-electricity united heating heat to substantially reduce the time of reactor start-up.
Accompanying drawing explanation
Fig. 1 is the structural representation of the start and stop servicing unit for integral reactor of the present invention.
Fig. 2 integral reactor start-up course curve map.
Embodiment
Below in conjunction with accompanying drawing citing, the present invention is described in more detail:
Composition graphs 1, the import starting separation vessel 15 is connected with the outlet conduit of once through steam generator 4; The steam (vapor) outlet starting separation vessel 15 is connected with main steam line through steam valve 20; The hydrophobic outlet starting separation vessel 15 is connected with water storage tank 16; The outlet at bottom of water storage tank 16 is connected with water circulating pump 17; Water circulating pump 17 is connected with once through steam generator 4 import feedwater piping by circulating water flow control valve 18; Water circulating pump 17 exports also has a road pipeline to be connected with water storage tank 16 by recirculation water flowrate control valve 19; Water storage tank 16 outlet has a road pipeline to be connected with condenser 22 by water storage tank outlet shutoff valve 25, water storage tank level control valve 26 and desuperheat dropping equipment 27; Feed pump 23 is connected with secondary circuit condensate system, and is connected with once through steam generator 4 inlet pipeline by main feed valve 24; Circulating water flow control valve 18, recirculation flow control valve 19 are connected with steam generator feed water control system with main feed valve 24; Water storage tank level control valve 26, steam valve 20 and cold valves 28 are connected with water storage tank control pressurer system.Described startup separation vessel 15 is external steam-water separator, for vapour, gas-liquid two-phase liquid being separated in start-up course, after having started, by the switching of flowrate control valve 28 and flowrate control valve 29, startup separation vessel is exited secondary coolant circuit system.Described water circulating pump 17 is power-actuated water pump, it is characterized in that pump rotary speed opens at reactor, stops remaining constant in process, at once through steam generator 4, start between separation vessel 15 and water storage tank 16 and set up stable circulating water flow.A part of recirculated water, for the low Liquid level of water storage tank 16, when water storage tank 16 water level is lower than setting value, by regulating the aperture of recirculation water flowrate control valve 19, is returned water tank 16, being prevented water tank to be evacuated by described recirculation water flowrate control valve 19 again.The flow regulation circulating water flow control valve 18 of described steam generator feed water control system according to recirculation water and the aperture of main feed valve 24, ensure that steam generator import feedwater flow remains constant.Described water storage tank control pressurer system is for regulating the pressure of water storage tank 16, and when pressure is lower than restriction, cold valves 28 is opened and water tank is squeezed in part feedwater, improves pressure; When pressure is higher than limit value, water storage tank level control valve 26 or steam valve 20 are opened, and reduce tank pressure respectively by draining and steam discharge.
Representing the Cold Start of integral reactor in the curve map of Fig. 2 by important parameter, is procedure parameter and the relation of time in the integral reactor start-up course determined by simulator program.Be in full water state after reactor water-filling has been vented, voltage stabilizer does not have pressure control capability.First open voltage stabilizer shower valve 8, start main pump 3 high-speed cruising, drop into voltage stabilizer electrical heating elements 9, utilize the power of voltage stabilizer electric heating part and the mechanical work of main pump to carry out heat temperature raising boosting to primary Ioops Main Coolant.Along with the rising of primary Ioops coolant temperature, primary Ioops water volume expands, and pressure raises, and needs interruption to open letdown flow operation valve 11 and carries out draining, primary Ioops pressure is remained within prescribed limits.
In primary Ioops cooling medium increasing temperature and pressure process, be full of water in start and stop backup system, pressure controls by water storage tank altitude valve 26 and cold valves 28.Starting water circulating pump keeps the feedwater flow of 15% to run.The hot water of steam generator outlet enters water storage tank 16 through steam-water separator 15, is then recycled water pump 17 and again squeezes into steam generator 4, forms a circulation.When primary Ioops coolant temperature is lower than 233.0 DEG C (saturation temperature that 3.0MPa pressure is corresponding), start and stop backup system water temperature inside is almost identical with primary Ioops coolant temperature.Because circulating water temperature raises volumetric expansion, water storage tank control pressurer system regulates water storage tank altitude valve 26 to carry out draining, prevents water storage tank superpressure.Draining enters condenser 22 after desuperheat reducing transformer 27 step-down.
When primary Ioops coolant temperature reaches 210 DEG C, close voltage stabilizer shower valve 8, improve the power of voltage stabilizer electric heating part 9, widen the temperature difference between voltage stabilizer 8 and primary Ioops cooling medium gradually.When voltage stabilizer temperature reaches 240 DEG C, close voltage stabilizer electric heating part 9, open letdown flow operation valve 11 draining, set up voltage stabilizer air cavity.Then open voltage stabilizer electric heating part 9 and heat steam water interface in voltage stabilizer 8, make voltage stabilizer pressure increase to rated operating pressures.Need interruption to open letdown flow operation valve 11 draining in boost process, ensure voltage stabilizer water level.
After primary Ioops coolant pressure meets the demands, regulate reactor power control system 12 to make reactor critical, and lifting reactor capability carry out core heat temperature raising gradually.When primary Ioops coolant temperature is lower than the saturation temperature that 3.0MPa pressure is corresponding, secondary circuit recirculated water is single phase, carrys out pressure in stable water tank by the draining of water storage tank altitude valve 26; Along with the lasting increase of reactor capability, primary Ioops coolant temperature raises rapidly.Recirculated water in start and stop backup system is heated to state of saturation gradually, when steam generator 4 exports generation two-phase mixture, steam-water separator 15 pairs of two-phase fluids are separated, saturated vapour gathers at steam-water separator top, for steady pressure, water storage tank altitude valve 26 constantly draining makes steam-water separator 15 water level inside constantly decline, after water level meets the demands, main steam valve 20 can be opened be exhausted, by the pressure regulating the aperture of main steam valve 20 to ensure steam-water separator 15.
Along with the increase of reactor capability, steam production constantly raises, and the saturation water flow entering water storage tank 16 reduces, cause water level decreasing in water storage tank 16, now open recirculation flow control valve 19, make a part of recirculated water again flow into water tank 16, prevent water tank to be evacuated.Steam generator feedwater flow control system regulates circulating water flow control valve 18 and main feed valve 24 to cooperatively interact simultaneously, utilizes main feedwater to carry out the reduction of compensation cycle discharge, ensures that once through steam generator import feedwater flow remains unchanged.Along with the rising of reactor capability, main feedwater flow constantly increases, and circulating water flow reduces gradually, until steam generator feedwater is all given by main feedwater, the whole recirculation flow recovery tank 16 of recirculated water, steam generator feedwater is all produced as superheated vapor.Can close circulating water flow control valve 18 and water circulating pump 17, start and stop backup system exits by switching flowrate control valve 28 and flowrate control valve 29, and start-up course completes.In start-up course, the temperature of once through steam generator import feedwater is elevated to by subcooled water and is then transitioned into supercooled state again close to state of saturation.

Claims (4)

1. for a start and stop servicing unit for integral reactor, it is characterized in that: comprise and start separation vessel (15), water storage tank (16) and water circulating pump (17); The import starting separation vessel (15) is connected with the outlet conduit of once through steam generator (4), the steam (vapor) outlet starting separation vessel (15) is connected with main steam line through steam valve (20), and the hydrophobic outlet starting separation vessel (15) is connected with water storage tank (16); The outlet at bottom of water storage tank (16) is connected with water circulating pump (17), and water storage tank (16) outlet has a road pipeline to be connected with condenser (22) by water storage tank outlet shutoff valve (25), water storage tank level control valve (26) and desuperheat dropping equipment (27); Water circulating pump (17) is connected with once through steam generator (4) import feedwater piping by circulating water flow control valve (18); Feed pump (23) is connected with condenser (22) and passes through main feed valve (24) and is connected with once through steam generator (4) inlet pipeline, is connected with water storage tank (16) by cold valves (28); Circulating water flow control valve (18) is connected with steam generator feed water control system with main feed valve (24); Water storage tank level control valve (26), steam valve (20) and cold valves (28) are connected with water storage tank control pressurer system.
2. the start and stop servicing unit for integral reactor according to claim 1, it is characterized in that: water circulating pump (17) outlet also has a road pipeline to be connected with water storage tank (16) by recirculation water flowrate control valve (19), and recirculation water flowrate control valve (19) is connected with steam generator feed water control system.
3. the start and stop servicing unit for integral reactor according to claim 1 and 2, it is characterized in that: described water circulating pump (17) is power-actuated water pump, pump rotary speed opens at reactor, stop remaining constant in process, at once through steam generator (4), start between separation vessel (15) and water storage tank (16) and set up stable circulating water flow.
4. based on described in claim 1 for a cold start-up method for the integral reactor of the start and stop servicing unit of integral reactor, it is characterized in that:
(1) after reactor water-filling has been vented, reactor has been in full water state, opens voltage stabilizer shower valve, uses the power of voltage stabilizer electric heating part (9) and the mechanical work of main pump (3) to improve primary Ioops coolant temperature;
(2) while primary Ioops system increasing temperature and pressure, start and stop backup system water storage tank control pressurer system action regulating tank pressure meets the demands, water circulating pump (17) is opened, recirculated water enters once through steam generator (4) by water storage tank (16) through circulating water flow control valve (18), flowed back to water storage tank (16) after primary Ioops coolant heating, complete and once circulate;
(3) after voltage stabilizer (7) temperature meets the demands, set up voltage stabilizer (7) vapour chamber by letdown flow operation valve (11) draining, then utilize the power of voltage stabilizer electric heating part (9) to improve voltage stabilizer (7) pressure to rated operating pressures;
(4) adjust reactor power control system (12) realization response heap critical, promote reactor (1) power, realize core heat temperature raising, along with the raising of reactor capability, secondary circuit recirculated water produces boiling gradually;
(5) along with the lifting of reactor capability, steam generator feed water control system constantly adjusts the aperture of recirculation flow control valve (19), circulating water flow control valve (18) and main feed valve (24), ensures that once through steam generator import feedwater flow is stablized.
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Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6021493A (en) * 1983-07-15 1985-02-02 株式会社日立製作所 Automatic output regulator for reactor
JPS63196896A (en) * 1987-02-12 1988-08-15 株式会社東芝 Nuclear reactor output controller
CN102081059A (en) * 2010-11-25 2011-06-01 哈尔滨工程大学 Forced-convection heat transfer experimental device for strong inner heat source containing porous medium passage

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6021493A (en) * 1983-07-15 1985-02-02 株式会社日立製作所 Automatic output regulator for reactor
JPS63196896A (en) * 1987-02-12 1988-08-15 株式会社東芝 Nuclear reactor output controller
CN102081059A (en) * 2010-11-25 2011-06-01 哈尔滨工程大学 Forced-convection heat transfer experimental device for strong inner heat source containing porous medium passage

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN109404071A (en) * 2018-12-17 2019-03-01 广西电网有限责任公司电力科学研究院 A kind of discrimination method of PWR steam generator model time constant

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