CN216811806U - Thermoelectric water combined system suitable for large pressurized water reactor nuclear power unit - Google Patents
Thermoelectric water combined system suitable for large pressurized water reactor nuclear power unit Download PDFInfo
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Abstract
The utility model belongs to the technical field of pressurized water reactor nuclear power stations, and particularly relates to a combined heat, power and water system suitable for a large pressurized water reactor nuclear power unit. In the utility model, a nuclear power unit I and a nuclear power unit II form a nuclear steam supply system; the industrial steam production system consists of a superheater, a steam generator, a deaerator, a secondary feedwater heater, a primary feedwater heater and a secondary feedwater pump; the seawater desalination and desalination water supply system comprises a desalination water feed pump, a water feed tank, a desalination water facility, a seawater desalination facility, a heater, a seawater intake, a seawater outlet, a standby fresh water intake and a process water user; the drain pipeline returns to the condenser of the pressurized water reactor nuclear power generator set through the third regulating valve and the fourth regulating valve to form a steam condensate system. On the premise of ensuring the nuclear safety, the utility model ensures that the nuclear power unit has the capability of producing industrial steam and fresh water by a seawater desalination technology.
Description
Technical Field
The utility model belongs to the technical field of pressurized water reactor nuclear power stations, and particularly relates to a combined heat, power and water system suitable for a large pressurized water reactor nuclear power unit.
Background
The technical safety and reliability of the pressurized water reactor nuclear power unit are fully verified. At present, a pressurized water reactor nuclear power unit is mainly used for generating electricity at home, and is used for assisting to provide a small amount of hot water for a town hot water pipe network for warming residents. As the steam parameters of the pressurized water reactor nuclear power unit are low, no precedent exists in the field of industrial steam supply of the nuclear power unit, and a technical scheme for carrying out technical transformation on the pressurized water reactor nuclear power unit and producing industrial steam needs to be explored.
Conventional cogeneration succeeds in a thermal power generating unit, but the nuclear power generating unit cannot directly use two-loop steam as industrial steam in consideration of the particularity of the nuclear power generating unit, technical innovation must be carried out in consideration of key factors such as unit safety and radioactivity control, and the operation and maintenance safety of the nuclear power generating unit and industrial steam users is guaranteed.
The seawater desalination technology has mature application in China. And small-scale seawater desalination facilities are also built in part of nuclear power units. But there is no coupling scheme for producing fresh water by using nuclear energy steam.
SUMMERY OF THE UTILITY MODEL
The utility model aims to provide a nuclear energy comprehensive utilization process which is suitable for nuclear power, industrial steam and seawater desalination of a pressurized water reactor nuclear power unit, and the nuclear power unit has the capability of producing industrial steam and producing fresh water through a seawater desalination technology on the premise of ensuring nuclear safety. The utility model provides a technical scheme for comprehensive utilization of nuclear energy, can solve the environmental protection pressure of petrochemical industry, and can realize regional carbon peak reaching by assistance as soon as possible.
The technical scheme adopted by the utility model is as follows:
a combined heat and power system suitable for a large pressurized water reactor nuclear power unit comprises a nuclear steam supply system, an industrial steam production system, a seawater desalination and desalting water supply system and a steam condensate system, wherein the nuclear power unit I, the nuclear power unit II, a first regulating valve, a second regulating valve, a first stop valve and a second stop valve form a nuclear steam supply system; the industrial steam production system comprises a superheater, a steam generator, a deaerator, a secondary feedwater heater, a primary feedwater heater and a secondary feedwater pump; the seawater desalination and desalination system comprises a desalination water feed pump, a feed tank, a desalination facility, a seawater desalination facility, a heater, a third regulating valve, a fourth regulating valve, a seawater intake, a seawater outlet, a standby fresh water intake and a service water user; the drain pipe returns to the condenser of the pressurized water reactor nuclear power unit through a third regulating valve and a fourth regulating valve to form a steam condensate system.
In the nuclear steam supply system, the first nuclear power unit is communicated with the second nuclear power unit through a pipeline, and a first regulating valve, a first stop valve, a second stop valve and a second regulating valve are sequentially arranged on the pipeline.
The industrial steam production system is connected with the superheater through a pipeline on a communicating pipeline of a first stop valve and a second stop valve, the superheater is connected with the steam generator and forms a loop, the steam generator is connected with a second-level water supply heater and forms a loop, the second-level water supply heater is respectively connected with a first-level water supply heater, the superheater conveys steam to a steam user, the deaerator is respectively connected with the superheater, the second-level water supply heater and the first-level water supply heater, and a second-level water supply pump is arranged between the deaerator and the second-level water supply heater.
In the seawater desalination and desalination water supply system, a desalination water facility is respectively connected with a water supply tank, a seawater desalination facility, a heater, a fresh water intake and a production water user, wherein the water supply tank is connected with a primary water supply heater through a desalination water supply pump, the seawater desalination facility is respectively connected with the heater, a seawater intake and a seawater outlet, and the desalination water facility introduces seawater through the fresh water intake and delivers production books to the production water user.
In the steam condensate system, a primary water supply heater is respectively connected with a first nuclear power unit and a second nuclear power unit through pipelines, and a third regulating valve and a fourth regulating valve are respectively arranged on the two pipelines.
The heater is connected with the first-stage feed water heater and a connecting pipeline of the nuclear power unit I to heat the first-stage feed water heater and the nuclear power unit I.
Exhaust pipelines of a first high-pressure cylinder and a second high-pressure cylinder of the nuclear power unit are communicated through a pipeline, and a third regulating valve and a fourth regulating valve are arranged on the pipeline; and a downstream pipeline of the valve is communicated with the heater and is connected into a downstream pipe section of the regulating valve III of the steam condensate system.
Compared with the prior art, the utility model has the beneficial effects that:
(1) the utility model provides a combined heat, power and water system suitable for a large pressurized water reactor nuclear power unit, which is designed by coupling a pressurized water reactor nuclear power unit, a hot seawater desalination facility and an industrial steam production system for the first time in China;
(2) the utility model provides a combined heat and power system suitable for a large pressurized water reactor nuclear power unit, which is characterized in that two pressurized water reactor nuclear power stations 1 and 2 are technically improved at the same time, so that a single unit has the capacity of independently bearing the scale of continuously supplying industrial steam;
(4) the utility model provides a combined heat, power and water system suitable for a large pressurized water reactor nuclear power unit.A communication loop is arranged between a pressurized water reactor nuclear power station 1 and a pressurized water reactor nuclear power station 2, and a stop valve 3 and a stop valve 4 are arranged. The state of the stop valves 3 and 4 is adjusted according to the steam supply scale, the commissioning state of the pressurized water reactor nuclear power unit 1 and the pressurized water reactor nuclear power unit 2 can be controlled, and the states of no industrial steam supply of the pressurized water reactor nuclear power unit, industrial steam supply of a single reactor and industrial steam supply of a double reactor in a combined mode can be achieved.
(4) The utility model provides a combined heat and power system suitable for a large pressurized water reactor nuclear power unit, which is provided with an adjusting valve 1 and an adjusting valve 2, wherein when double-reactor combined industrial steam supply is carried out, the steam scale can be distributed by adjusting the opening degrees of the adjusting valve 1 and the adjusting valve 2, and the relation between steam supply and power generation between the pressurized water reactor nuclear power unit 1 and the pressurized water reactor nuclear power unit 2 is optimized, so that the optimal matching among a reactor, the power generation and the steam supply is achieved;
(5) the utility model provides a thermoelectric water combination system suitable for a large pressurized water reactor nuclear power unit, which is an industrial steam production system consisting of a superheater 5, a steam generator 6, a deaerator 7, a secondary feedwater heater 8, a primary feedwater heater 9 and a secondary feedwater pump 15. Through the mode of heating step by step, realize the heating of level four heat exchangers series connection, make full use of steam heat energy.
(6) The utility model provides a combined heat and power system suitable for a large pressurized water reactor nuclear power unit, which is characterized in that main steam heats saturated steam in a superheater 5 to form superheated industrial steam with a certain superheat degree and is conveyed to a steam-using enterprise through a long-distance conveying pipe network, and part of the main steam is connected with a deaerator through a branch for heating feedwater and deaerating. In the heat exchanger 5, a phase change will occur on the high temperature steam side.
(7) The utility model provides a thermoelectricity water combination system suitable for a large pressurized water reactor nuclear power unit, which is provided with a steam generator 6, a deaerator 7, a secondary water supply heater 8, a primary water supply heater 9 and a secondary water supply pump 15, wherein after main steam heated by a superheater 5 is changed into high-temperature saturated water, the main steam heats the water supply in the steam generator 6, the secondary water supply heater 8 and the primary water supply heater 9 step by step, the energy of the main steam is fully utilized, in an evaporator 6, the water supply is heated into saturated steam, and the low-temperature side of the evaporator is subjected to phase change.
(8) The utility model provides a thermoelectric water combined system suitable for a large pressurized water reactor nuclear power unit, which is provided with a steam condensate system, wherein main steam condensate after being heated step by step passes through a drain pipeline and returns to a two-loop conventional island condensate system of a pressurized water reactor nuclear power unit 1 and a pressurized water reactor nuclear power unit 2 through the drain pipeline. The valves 22 and 23 can be arranged on the pipeline, the opening and closing states of the valves 22 and 23 can be adjusted according to the running state of the nuclear power generating unit, the water quantity returned to the nuclear power generating unit is adjusted, and the nuclear power generating unit 1 and the nuclear power generating unit 2 are guaranteed to run in a favorable steam-water balance state.
(9) The utility model provides a combined heat and power system suitable for a large pressurized water reactor nuclear power unit, which is provided with a valve 16 and a valve 17. The high-pressure cylinder exhaust pipeline of the pressurized water reactor nuclear power unit 1 and the pressurized water reactor nuclear power unit 2 is technically improved, two control valves of a valve 16 and a valve 17 are added, and the operating state control of the pressurized water reactor nuclear power unit 1 and the pressurized water reactor nuclear power unit 2 can be realized by controlling the opening and closing state of the control valves, so that the seawater desalination facility is ensured to be always kept in steam supply.
(10) The utility model provides a combined heat and power system suitable for a large pressurized water reactor nuclear power unit, which is provided with a heater 14, wherein the heater 14 is arranged, and low-quality saturated steam generated by steam conversion is used for a hot-method seawater desalination facility because the seawater desalination facility cannot directly use steam in a secondary loop of a nuclear power unit as a hot-method seawater desalination steam source.
(11) The utility model provides a combined heat and power system suitable for a large pressurized water reactor nuclear power unit, which is provided with a seawater desalination implementation 13, a demineralized water feed pump 10, a water feed tank 11, a demineralized water facility 12, a seawater intake 18, a seawater outlet 19, a standby fresh water intake 20 and a production water user 21. Wherein the seawater desalination facility adopts a thermal process, and fully utilizes the steam waste heat of the pressurized water reactor nuclear power generator set; desalting fresh water produced by the seawater desalination facility by a desalting water facility, and supplying the desalted water to plant area production water users 21 of the nuclear power station, industrial steam production water and seawater desalination low-pressure steam source water; the concentrated seawater is treated by the concentrated seawater treatment system and then discharged through the seawater outlet 19.
(12) The utility model provides a combined heat and power system suitable for a large pressurized water reactor nuclear power unit, which is provided with a spare fresh water intake 20 and can be independently used as a water source of a desalted water facility. The seawater desalination device 13 is used for standby, so that the safety and reliability of the incoming water of the desalination device 12 are ensured, and the sufficient supply of the desalination water of the whole system is ensured.
(13) The utility model provides a thermoelectric water combination system suitable for a large pressurized water reactor nuclear power unit, wherein a seawater intake 18 is arranged in a circulating water drainage tunnel of the nuclear power unit, the temperature of the taken seawater is the temperature drainage of the nuclear power unit, the influence of the temperature drainage on a sea area can be reduced, the partial waste heat of the nuclear power unit is utilized, and the heat utilization rate of the nuclear power unit is improved.
Drawings
FIG. 1 is a schematic structural diagram of a combined heat and power system suitable for a large pressurized water reactor nuclear power unit according to the present invention;
in the figure: 1-a first regulating valve, 2-a second regulating valve, 3-a first stopping valve, 4-a second stopping valve, 5-a superheater, 6-a steam generator, 7-a deaerator, 8-a second stage feed water heater, 9-a first stage feed water heater, 10-a demineralized water feed pump, 11-a feed water tank, 12-a demineralized water facility, 13-a seawater desalination facility, 14-a heater, 15-a second stage feed water pump, 16-a second regulating valve, 17-a second regulating valve, 18-a seawater intake, 19-a seawater outlet, 20-a standby fresh water intake, 21-a production water user, 22-a third regulating valve, 23-a fourth regulating valve, 24-a first nuclear power unit, 25-a second nuclear power unit and 26-a steam user.
Detailed Description
The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
In the description of the present invention, it should be noted that the terms "center", "upper", "lower", "left", "right", "vertical", "horizontal", "inner", "outer", etc., indicate orientations or positional relationships based on the orientations or positional relationships shown in the drawings, and are only for convenience of description and simplicity of description, but do not indicate or imply that the device or element being referred to must have a particular orientation, be constructed and operated in a particular orientation, and thus, should not be construed as limiting the present invention. Furthermore, the terms "first," "second," and "third" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance.
In the description of the present invention, it should be noted that, unless otherwise explicitly specified or limited, the terms "mounted," "connected," and "connected" are to be construed broadly, e.g., as meaning either a fixed connection, a removable connection, or an integral connection; can be mechanically or electrically connected; they may be connected directly or indirectly through intervening media, or they may be interconnected between two elements. The specific meanings of the above terms in the present invention can be understood in specific cases to those skilled in the art.
As shown in figure 1, the combined heat, power and water system suitable for a large pressurized water reactor nuclear power unit provided by the utility model comprises a nuclear steam supply system, an industrial steam production system, a seawater desalination and desalting water supply system and a steam condensate system, the system specifically comprises a first nuclear power unit 24, a second nuclear power unit 25, a first regulating valve 1, a second regulating valve 2, a first stop valve 3, a second stop valve 4, a superheater 5, a steam generator 6, a deaerator 7, a second-stage feed water heater 8, a first-stage feed water heater 9, a demineralized water feed pump 10, a feed water tank 11, a demineralized water facility 12, a seawater desalination facility 13, a heater 14, a second-stage feed water pump 15, a third regulating valve 16, a fourth regulating valve 17, a seawater intake 18, a seawater outlet 19, a standby freshwater intake 20, a production water user 21, a third regulating valve 22, a fourth regulating valve 23 and a steam user 26.
The nuclear power generating unit I24, the nuclear power generating unit II 25, the first regulating valve 1, the second regulating valve 2, the first stop valve 3 and the second stop valve 4 form a nuclear steam supply system;
the industrial steam production system is composed of a superheater 5, a steam generator 6, a deaerator 7, a secondary feedwater heater 8, a primary feedwater heater 9 and a secondary feedwater pump 15;
a desalted water supply system is composed of a desalted water supply pump 10, a water supply tank 11, a desalted water facility 12, a seawater desalination facility 13, a heater 14, a third regulating valve 16, a fourth regulating valve 17, a seawater intake 18, a seawater outlet 19, a standby fresh water intake 20 and a production water user 21;
and the drain pipe returns to a condenser of a pressurized water reactor nuclear power unit through a third regulating valve 22 and a fourth regulating valve 23 to form a steam condensate system.
The nuclear power generating set I24 is communicated with a nuclear power generating set II 25 through a pipeline, and a first regulating valve 1, a first stop valve 3, a second stop valve 4 and a second regulating valve 2 are sequentially arranged on the pipeline;
an industrial steam production system is characterized in that a communicating pipeline of a first stop valve 3 and a second stop valve 4 is connected with a superheater 5 through a pipeline, the superheater 5 is connected with a steam generator 6 to form a loop, the steam generator 6 is connected with a second-stage feed water heater 8 to form a loop, the second-stage feed water heater 8 is respectively connected with a first-stage feed water heater 9, the superheater 5 conveys steam to a steam user 26, a deaerator 7 is respectively connected with the superheater 5, the second-stage feed water heater 8 and the first-stage feed water heater 9, and a second-stage feed water pump 15 is arranged between the deaerator 7 and the second-stage feed water heater 8;
a seawater desalination and desalination water supply system, wherein a desalination water facility 12 is respectively connected with a water supply tank 11, a seawater desalination facility 13, a heater 14, a fresh water intake 20 and a production water user 21, wherein the water supply tank 11 is connected with a primary water supply heater 9 through a desalination water supply pump 10, the seawater desalination facility 13 is respectively connected with the heater 14, a seawater intake 18 and a seawater exhaust 19, the desalination water facility 12 introduces seawater through the fresh water intake 20 and delivers production books to the production water user 21;
in the steam condensate system, a primary water supply heater 9 is respectively connected with a first nuclear power unit 24 and a second nuclear power unit 25 through pipelines, and a third regulating valve 22 and a fourth regulating valve 23 are respectively arranged on the two pipelines;
the heater 14 is connected with the first-stage feed water heater 9 and a connecting pipeline of the nuclear power unit I24 to heat the first-stage feed water heater;
exhaust pipelines of a first 24 and a second 25 high-pressure cylinder of the nuclear power unit are communicated through a pipeline, and a third regulating valve 16 and a fourth regulating valve 17 are arranged on the pipeline; the downstream line of the valve is communicated with the heater 14 and is connected to the downstream pipe section of the regulating valve III 22 of the steam condensate system.
The working principle of the utility model is as follows:
through transformation, the nuclear power unit 1 is communicated with the nuclear power unit 2 through the first regulating valve 1 and the first stop valve 3 through the second regulating valve 2 and the second stop valve 4, and a communication loop is established between a communication pipeline and a unit condensate system through the superheater 5, the steam generator 6, the secondary feed water preheater 8, the secondary feed water pump 15, the deaerator 7, the primary feed water heater 9. The secondary nuclear power unit 1 is communicated with the nuclear power unit 2 through a fourth regulating valve 17 through a second throttle valve 16, and a communication pipeline passes through a heater 14 to establish a communication loop with a unit condensate system. Seawater is conveyed from a seawater intake 18 to a seawater desalination facility 13 through a pipeline, the generated concentrated seawater is sent to a seawater discharge outlet 19, and the generated fresh water passes through a desalination facility 12 and then is sent to users in three ways: one path of the industrial steam is heated step by step to produce industrial steam through a water supply tank 11, a demineralized water feed pump 10, a primary water supply heater 9, a deaerator 7, a secondary water supply pump 15, a secondary water supply heater 8, a steam generator 6 and a superheater 5; one path of the steam is used as a steam source of a hot sea desalination facility through a heater 14 and a sea water desalination facility 13; one is sent to the process water user 21. To ensure the reliability of the supply of desalinated water, a backup fresh water intake 20 is connected to the desalinated water facility 12 as a backup source of fresh water produced by the seawater desalination implementation 13.
The nuclear steam supply system comprises a nuclear power unit 1, a nuclear power unit 2, a first regulating valve 1, a second regulating valve 2, a first stop valve 3 and a second stop valve 4. Partial main steam extracted from the conventional island main steam system of the pressurized water reactor nuclear power unit 1 is conveyed to a front steam collecting pipe of the heat exchange equipment through a first adjusting valve 1 and a first stop valve 3 through technical transformation, and partial main steam extracted from the conventional island main steam system of the pressurized water reactor nuclear power unit 2 is conveyed to the front steam collecting pipe of the heat exchange equipment through a second adjusting valve 2 and a second stop valve 4.
The industrial steam production system comprises a superheater 5, a steam generator 6, a deaerator 7, a secondary feedwater heater 8, a primary feedwater heater 9 and a secondary feedwater pump 15. The desalted water from the seawater desalination and desalted water supply system is heated by a water feed pump 10 through a primary preheater and is sent into a deaerator for deoxidization, then the desalted water is boosted by a secondary water feed pump and is sent into a steam generator after passing through a secondary water feed preheater, the heat released by main steam is taken away and is converted into industrial steam with a certain superheat degree, and the continuous heat exchange process realizes the continuous supply of the industrial steam.
The steam condensate system comprises a drain pipeline and a unit condensate system, heat released by main steam in the steam conversion equipment is changed into condensate, and the condensate returns to the two-loop conventional island condensate system of the pressurized water reactor nuclear power unit 1 and the pressurized water reactor nuclear power unit 2 through a pipeline passing through a third regulating valve 22 and a fourth regulating valve 23 and finally returns to the condenser.
The seawater desalination and desalination water supply system comprises a desalination water feed pump 10, a water feed tank 11, a desalination water facility 12, a seawater desalination facility 13, a heater 14, a third regulating valve 16, a fourth regulating valve 17, a seawater intake 18, a seawater outlet 19, a standby fresh water intake 20 and a process water user 21, wherein desalination water is heated in the heater 14 through exhaust of a high-pressure cylinder of an extraction unit to generate low-pressure steam for the thermal process seawater desalination facility 13, and condensed water generated by the heater 14 returns to the unit condensed water system through a drain pipeline, a regulating valve three 22 and a regulating valve four 23. The desalted water produced by the desalted water facility 12 is divided into three paths, one path is conveyed to the industrial steam production system through the water feeding pump 10, the other path is used for producing a seawater desalination steam source through the heat exchanger 14, and the other path is used for producing water for the water production user 21. The seawater desalination facility 13 and the standby fresh water intake 20 are standby water sources for the desalination facility 12, and the seawater desalination facility produces concentrated seawater and the like which are discharged to the sea through the seawater outlet 19.
The utility model provides a combined production process of thermoelectricity and water suitable for a large pressurized water reactor nuclear power unit, which comprises 3 stages and mainly comprises a stage of normally putting a pressurized water reactor nuclear power unit I24 and a stage of normally putting the pressurized water reactor nuclear power unit I25, wherein a seawater desalination facility and a desalination water system are put into operation with the seawater desalination facility after the nuclear power unit is stably operated, and a nuclear steam supply system and an industrial steam production system are synchronously put into operation after the desalination water system is stabilized. The method specifically comprises the following steps:
the first stage is as follows: normally operating a pressurized water reactor nuclear power unit I24 and a pressurized water reactor nuclear power unit II 25;
(a) closing the first regulating valve 1, the second regulating valve 2, the first stop valve 3, the second stop valve 4, the third regulating valve 16, the fourth regulating valve 17, the third regulating valve 22 and the third regulating valve 23;
(b) checking and confirming the state of the nuclear power unit collision port modified pipeline, and confirming that nuclear steam supply is not communicated;
(c) and (3) according to a unit starting process, operating the first pressurized water reactor nuclear power unit 24 and the second pressurized water reactor nuclear power unit 25 at full power.
And a second stage: commissioning seawater desalination facilities and desalination facilities:
(a) checking the state of the drain pipeline and the pipeline of the conventional island unit to ensure that the pipelines are communicated;
(b) leading out the water supply of the standby fresh water intake 20 to the heater 14 through the pipeline of the nuclear power plant; introducing seawater into the seawater desalination plant 13 through a seawater desalination intake 18;
(c) determining a steam source of a seawater desalination facility according to the steam commissioning scale, opening a fourth regulating valve 17, and closing a third regulating valve 16 (taking a pressurized water reactor nuclear power unit I24 as an example, if a pressurized water reactor nuclear power unit II 25 is taken as a heat source, the states of the fourth regulating valve 17 and the third regulating valve 16 are opposite);
(d) monitoring the outlet parameters of the heater 14, and when the quality required by seawater desalination is met, putting the seawater desalination facility 13 into operation. Monitoring the quality of the fresh water of the effluent of the seawater desalination facility;
(e) introducing fresh water produced by a seawater desalination facility 13 into a desalted water facility 12, monitoring the effluent quality of the desalted water facility and introducing desalted water into a feed tank 11;
(f) monitoring the water level and the capacity of a water supply tank 11, closely paying attention to the water level of the water tank, and turning on a demineralized water supply pump 10 when the water storage capacity meets the requirement of starting an industrial steam production system;
and a third stage: commissioning nuclear steam supply system and industrial steam production system
(a) Checking that the states of the first regulating valve 1, the first stop valve 3, the second regulating valve 2 and the second stop valve 4 are closed;
(b) according to the operation decision, determining an industrial load supporting unit and determining the opening requirements of a first regulating valve 1 and a second regulating valve 2;
(c) monitoring and confirming that pipelines of a nuclear steam supply system and an industrial steam production system are kept smooth;
(d) according to the water supply condition of a demineralized water system, when a demineralized water feed pump 10 is started, a first adjusting valve 1, a second adjusting valve 2, a first stop valve 3 and a second stop valve 4 are opened to monitor nuclear steam parameters (taking the example that two units are put into operation and bear industrial steam load as an example);
(e) the inlet and outlet parameters of the superheater 5, the steam generator 6, the deaerator 7, the secondary feed water heater 8 and the primary feed water heater 9 are monitored, so that the outlet of the superheater 5 meets the requirements of industrial steam users, and the unit can operate with a seawater desalination system and an industrial steam system at the same time.
(4) Monitoring unit operation parameters, adjusting and cutting off operation unit according to unit operation state
(a) Monitoring inlet and outlet parameters of the superheater 5, the steam generator 6, the deaerator 7, the secondary feed water heater 8 and the primary feed water heater 9, ensuring that an outlet of the superheater 5 meets the requirements of industrial steam users, and realizing that a unit simultaneously has a seawater desalination system and an industrial steam system to operate;
(b) when the industrial steam load is adjusted, according to an operation decision, determining an industrial load supporting unit and determining the opening requirements of a first regulating valve 1 and a second regulating valve 2;
(c) adjusting the opening of the regulating valve to enable the steam load to be matched with the power of the unit reactor and the power generation power;
(d) when one unit can meet the load requirement (or one nuclear power unit is about to enter a overhaul state), closing the first stop valve 3 (or the second stop valve 4) step by step to cut off one nuclear power unit;
taking the technical transformation of the VVER type pressurized water reactor nuclear power unit as an example, the main steam collecting pipe of the VVER type pressurized water reactor nuclear power unit is technically transformed according to the scheme, main steam is led out, low-pressure superheated industrial steam is produced through a steam conversion system and is conveyed to a user enterprise in a petrochemical industry base through a long conveying pipeline. The utility model realizes the coupling of the technical schemes of nuclear power, seawater desalination and industrial steam, provides a new idea and demonstration project for comprehensive utilization of nuclear energy, and provides reference for technical transformation of a pressurized water reactor nuclear power unit.
It will be evident to those skilled in the art that the utility model is not limited to the details of the foregoing illustrative embodiments, and that the present invention may be embodied in other specific forms without departing from the spirit or essential attributes thereof. The present embodiments are therefore to be considered in all respects as illustrative and not restrictive, the scope of the utility model being indicated by the appended claims rather than by the foregoing description, and all changes which come within the meaning and range of equivalency of the claims are therefore intended to be embraced therein. Any reference sign in a claim should not be construed as limiting the claim concerned.
Furthermore, it should be understood that although the present description refers to embodiments, not every embodiment may contain only a single embodiment, and such description is for clarity only, and those skilled in the art should integrate the description, and the embodiments may be combined as appropriate to form other embodiments understood by those skilled in the art.
Claims (7)
1. The utility model provides a thermoelectricity water combined system suitable for large-scale pressurized water reactor nuclear power unit which characterized in that: the system comprises a nuclear steam supply system, an industrial steam production system, a seawater desalination and desalting water supply system and a steam condensate system, wherein the nuclear steam supply system consists of a nuclear power unit I (24), a nuclear power unit II (25), a first regulating valve (1), a second regulating valve (2), a first stop valve (3) and a second stop valve (4); the industrial steam production system is composed of a superheater (5), a steam generator (6), a deaerator (7), a secondary water supply heater (8), a primary water supply heater (9) and a secondary water supply pump (15); a seawater desalination and desalination supply system is composed of a desalination water feed pump (10), a feed tank (11), a desalination facility (12), a seawater desalination facility (13), a heater (14), a third regulating valve (16), a fourth regulating valve (17), a seawater intake (18), a seawater outlet (19), a standby fresh water intake (20) and a service water user (21); and the drain pipeline returns to a condenser of a pressurized water reactor nuclear power unit through a third regulating valve (22) and a fourth regulating valve (23) to form a steam condensate system.
2. The combined heat and power system applicable to the large pressurized water reactor nuclear power unit as claimed in claim 1, wherein: in the nuclear steam supply system, a first nuclear power unit (24) is communicated with a second nuclear power unit (25) through a pipeline, and a first regulating valve (1), a first stop valve (3), a second stop valve (4) and a second regulating valve (2) are sequentially arranged on the pipeline.
3. The combined heat and power system applicable to the large pressurized water reactor nuclear power unit as claimed in claim 2, wherein: industrial steam production system, on the communicating pipe way of stop valve one (3) and stop valve two (4), be connected with over heater (5) through the pipeline, over heater (5) are connected and constitute the return circuit with steam generator (6), steam generator (6) are connected and constitute the return circuit with second grade feedwater heater (8), second grade feedwater heater (8) are connected with one-level feedwater heater (9) respectively, over heater (5) are carried steam for steam consumer (26), oxygen-eliminating device (7) respectively with over heater (5), second grade feedwater heater (8), one-level feedwater heater (9) are connected, be equipped with second grade feedwater pump (15) between oxygen-eliminating device (7) and second grade feedwater heater (8).
4. The combined heat, power and water system suitable for the large pressurized water reactor nuclear power unit as claimed in claim 3, wherein: according to the seawater desalination and desalination water supply system, a desalination water facility (12) is respectively connected with a water supply tank (11), a seawater desalination facility (13), a heater (14), a fresh water intake (20) and a production water user (21), wherein the water supply tank (11) is connected with a primary water supply heater (9) through a desalination water supply pump (10), the seawater desalination facility (13) is respectively connected with the heater (14), a seawater intake (18) and a seawater outlet (19), and the desalination water facility (12) introduces seawater through the fresh water intake (20) and conveys production books to the production water user (21).
5. The combined heat and power system applicable to the large pressurized water reactor nuclear power unit as claimed in claim 4, wherein: in the steam condensate system, a primary water supply heater (9) is respectively connected with a nuclear power unit I (24) and a nuclear power unit II (25) through pipelines, and a regulating valve III (22) and a regulating valve IV (23) are respectively arranged on the two pipelines.
6. The combined heat and power system applicable to the large pressurized water reactor nuclear power unit as claimed in claim 5, wherein: and the heater (14) is connected with the primary water supply heater (9) and a connecting pipeline of the nuclear power unit I (24) to heat the primary water supply heater and the nuclear power unit I.
7. The combined heat and power system applicable to the large pressurized water reactor nuclear power unit as claimed in claim 6, wherein: exhaust pipelines of high-pressure cylinders of the nuclear power unit I (24) and the nuclear power unit II (25) are communicated through a pipeline, and a third regulating valve (16) and a fourth regulating valve (17) are arranged on the pipeline; the downstream pipeline of the valve is communicated with the heater (14) and is connected into the downstream pipe section of the regulating valve III (22) of the steam condensate system.
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| CN202122814368.XU CN216811806U (en) | 2021-11-16 | 2021-11-16 | Thermoelectric water combined system suitable for large pressurized water reactor nuclear power unit |
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