CN111396156A - Multi-unit heating system of nuclear power plant with steam side unit system and water side combined system - Google Patents
Multi-unit heating system of nuclear power plant with steam side unit system and water side combined system Download PDFInfo
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- CN111396156A CN111396156A CN202010318895.9A CN202010318895A CN111396156A CN 111396156 A CN111396156 A CN 111396156A CN 202010318895 A CN202010318895 A CN 202010318895A CN 111396156 A CN111396156 A CN 111396156A
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K13/00—General layout or general methods of operation of complete plants
- F01K13/02—Controlling, e.g. stopping or starting
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K13/00—General layout or general methods of operation of complete plants
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K17/00—Using steam or condensate extracted or exhausted from steam engine plant
- F01K17/02—Using steam or condensate extracted or exhausted from steam engine plant for heating purposes, e.g. industrial, domestic
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K21/00—Steam engine plants not otherwise provided for
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B1/00—Methods of steam generation characterised by form of heating method
- F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
- F22B1/16—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being hot liquid or hot vapour, e.g. waste liquid, waste vapour
- F22B1/162—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being hot liquid or hot vapour, e.g. waste liquid, waste vapour in combination with a nuclear installation
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F24—HEATING; RANGES; VENTILATING
- F24D—DOMESTIC- OR SPACE-HEATING SYSTEMS, e.g. CENTRAL HEATING SYSTEMS; DOMESTIC HOT-WATER SUPPLY SYSTEMS; ELEMENTS OR COMPONENTS THEREFOR
- F24D1/00—Steam central heating systems
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- High Energy & Nuclear Physics (AREA)
- Life Sciences & Earth Sciences (AREA)
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- Sustainable Energy (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a multi-unit heating system of a nuclear power plant with steam side unit system and water side combined system, wherein the nuclear power plant comprises more than one unit with the same structure, each unit is provided with a primary loop and two loops, and the multi-unit heating system is characterized in that each unit comprises a water feeding pump for conveying water in the two loops to a steam generator, the outlet end of the steam generator is sequentially connected with a high pressure cylinder, a low pressure cylinder, a condenser and the water feeding pump to form closed circulation, the output end of the low pressure cylinder is connected with a generator, and the low pressure cylinder is connected with a steam side heat exchange pipeline in a steam-water heat exchanger in parallel; water side heat exchange pipelines in the steam-water heat exchangers in all the units are connected in parallel and then are connected with a heat supply network circulating pump in a heat supply network circulating pump station to form a loop. The invention solves the problem of reliability of a heat supply source side by using an operation mode that two units are used and one standby or a plurality of units are used and one standby and a steam side unit system, and simultaneously solves the problem of heat supply interruption caused by overlong standby heat source operation time, and is clean, stable and efficient.
Description
Technical Field
The invention relates to a multi-unit heating system of a nuclear power plant, which is manufactured by combining a steam side unit system and a water side system, and belongs to the technical field of nuclear power equipment.
Background
The external heat supply of the nuclear power plant is basically the same as the external heat supply of the conventional thermal power plant in principle, partial heat is extracted from the heat-electricity conversion of the power plant, and the heating to a local place in winter is realized while the conventional power generation is realized. However, the heat supply of the nuclear power unit is different from the heat supply of the conventional thermal power unit to a certain extent based on the particularity of the nuclear power unit (for example, the maintenance period of the unit is relatively fixed, so that the heating season conflicts with a unit material change overhaul window, the area of an essential area is limited due to the division of an entity protection area, the arrangement of facilities in a site is compact, the large-scale heat exchange initial station cannot be arranged, and the like).
After the conventional thermal power generating unit is subjected to thermal power cogeneration, in order to effectively guarantee the heating load of the unit in winter, a shutdown maintenance window of the thermal power generating unit is usually required to be adjusted to avoid the heating season, so that the reliability of a heat source in the heating season is effectively guaranteed.
The refueling overhaul period of the AP1000 nuclear power plant unit is 18 months, and the adjustment of the refueling overhaul period brings the fuel consumption depth change of a reactor, and has adverse effects on the running cost of the unit, the arrangement of fuel assemblies after refueling and the like.
A nuclear power plant area is divided into an essential area, a protection area and a control area, and an AP1000 nuclear power unit nuclear island plant and a conventional island plant are arranged in the essential area. In a conventional power plant heat supply scheme, unit extraction steam is used as a heating source, and heating heat supply network circulating water realizes external heat supply, so that heat exchange stations are required to be arranged around the unit, and a steam-water heat exchanger, a heat supply network circulating pump, a heat supply network water replenishing pump and other equipment are arranged. Because factory building, equipment arrangement are compact in the essential area of nuclear power plant, can't arrange large-scale heat transfer station, will lead to the steam conduit longer again to arranging the heat transfer station outside the essential area, bring the steam conduit to deposit the big machine set overspeed's of steam turbine tripping operation back safety risk, the system is put into operation initial stage and is washed, the warm pipe time is longer, can't in time put into reserve and a series of problems such as the hydrophobic quality of water is unqualified for a long time in the system operation stage demineralized water loss is big, the heat loss.
Disclosure of Invention
The technical problem to be solved by the invention is as follows: the existing large nuclear power unit directly applies the conventional cogeneration heating mode of a power plant to supply heat externally, and has the problems of low safety, reliability and economy.
In order to solve the technical problems, the invention provides a multi-unit heating system of a nuclear power plant with a steam side unit system and a water side combined system, wherein the nuclear power plant comprises more than one unit with the same structure, system and parameter, and each unit is provided with a primary loop and two loops; water side heat exchange pipelines in the steam-water heat exchangers in all the units are connected in parallel and then are connected with a heat supply network circulating pump in a heat supply network circulating pump station to form a loop.
Preferably, the system is characterized in that the heat supply network circulating pump is sequentially connected with a constant pressure pump and a dirt remover in series, and the constant pressure pump is connected with the deaerator.
Preferably, the three circuits and other circuits at the downstream are respectively communicated with two heat exchange pipelines of the water-water heat exchanger (13) to exchange heat.
Preferably, the water in the second loop of the nuclear power plant is boosted by a water supply pump and then is conveyed to a steam generator, the steam generator absorbs heat to become saturated steam, the saturated steam sequentially enters a high-pressure cylinder and a low-pressure cylinder to do work to push the steam turbine to rotate, the steam turbine drives a generator to generate electricity, the steam after doing work enters a condenser, the heat is exchanged to seawater in the third loop and then is condensed into water, and the water is conveyed to the steam generator by the water supply pump after being heated step by step to complete closed circulation of the whole second loop; the return water of the circulating water of the heat supply network in the water side heat exchange pipeline in the steam-water heat exchanger firstly enters the heat supply network circulating pump, is boosted by the heat supply network circulating pump and is respectively conveyed to the two units, so that the heat supply requirements of the two units are met.
Preferably, when the nuclear power plant normally operates, the steam-water heat exchanger in any unit of the nuclear power plant operates, and other steam-water heat exchangers do not operate and are standby.
Preferably, the steam-side heat exchange pipeline of the steam-water heat exchanger in the unit is provided with a valve a, the water-side heat exchange pipeline is respectively provided with a valve b and a valve c, the valve a, the valve b and the valve c in the unit in normal operation are in an open state, and the valve a, the valve b and the valve c in the standby unit are in a closed state.
More preferably, the three-circuit water-feeding heat exchanger is characterized in that a valve d and a valve e are respectively arranged on two sides of the three-circuit water-feeding heat exchanger, the valve d and the valve e are in an open state in normal operation, and the valve d and the valve e are in a closed state in abnormal conditions, for example, when an accident occurs and isolation is required, the three-circuit water-feeding heat exchanger is used for cutting off the communication state between the three circuits and the downstream circuit.
The nuclear power unit supplies heat to the outside, and the refueling period is relatively fixed, the heat supply load is large, so the reliability of heat supply needs to be guaranteed through heat source measurement, and therefore the invention adopts a one-use one-standby operation mode.
By adopting the steam side unit system scheme, the water balance of the two loops of each unit can be effectively ensured, and the problems of water and steam crossing between units caused by a main pipe system are prevented. Under the working condition that the unit is used for one time and is standby for one time, if a heat supply system of the standby unit is in a cold standby state, the steam extraction point caused by the main pipe system is far away from the steam main pipe, so that the problems that a steam pipeline is washed, the time for heating the pipe is too long and the standby unit cannot be put into normal operation in time are caused in the switching process of the heat supply unit; if the heat supply system of the standby unit is in a hot standby state, the steam extraction point caused by the main pipe is far away from the steam main pipe, so that the heat loss caused by steam drainage of the pipeline of the standby heat supply unit is serious, and the economical efficiency is poor. Therefore, the invention provides a steam side unit system scheme, each unit is additionally provided with an adjacent house in a steam turbine plant, and the heat supply network heater is arranged around a steam extraction point of the steam turbine and a drainage point of a condenser, so that the problems of heat loss caused by a main pipe system, long operation time of a standby unit and the like can be effectively solved, meanwhile, the length of a steam pipeline arranged in a plant area can be effectively shortened, the pipeline investment is reduced, and the operation reliability is improved; because the heat supply network heater is arranged around the condenser, the drainage recovery can be directly realized through the pressure difference, the investment of the drainage pump equipment is reduced, and the economy is further improved.
By adopting the water side combined scheme, the problem that equipment such as a heat supply network circulating pump, a water replenishing pump, a deaerator, a heat supply network heater and the like cannot be arranged in the critical area due to limited arrangement space of the critical area can be effectively solved. The heat supply network heater is arranged in the critical area, so that the heat loss of the pipeline is reduced, and the heat supply economy is improved; the heat supply network circulating pump, the heat supply network water replenishing pump and the heat supply network deaerator are arranged outside the key area, the plant area arrangement space is reasonably utilized, a water side combined scheme is adopted, the heat supply reliability can be effectively improved, and the two units share equipment such as the heat supply network circulating pump and the like, so that the heat supply economical efficiency is improved.
The invention solves the problem of reliability of a heat supply source side by using an operation mode that two units are used and one standby or a plurality of units are used and one standby and a steam side unit system, and simultaneously solves the problem of heat supply interruption caused by overlong standby heat source operation switching time. The multi-unit heating system of the nuclear power plant, which is manufactured by combining the steam side unit system and the water side system, ensures the safety and the reliability, and has the advantages of cleanness, stability, high efficiency and the like.
Compared with the prior art, the invention has the beneficial effects that:
1. steam side unit system, heater arranged in critical area, shortened steam pipeline length
The steam side adopts the unit system, ensures that the effective isolation of heat supply unit inter-block two return circuits, improves reliability and security, and the heater arranges in the area of wanting to damage, is close to steam turbine extraction point and condenser drainage point, reduces pipeline investment and steam heat waste, guarantees the hydrophobic quality of water of heat supply steam, shortens reserve switching time, effectively guarantees the corresponding speed of accident.
2. The heat supply network drainage pump is eliminated, and the economical efficiency is improved
The heat supply network heater is arranged in the critical area and is close to a steam extraction point of the steam turbine and a drainage point of the condenser, and drainage and self-flow are realized by utilizing the pressure difference between the steam side of the heat supply network heater and the condenser, so that the economical efficiency is effectively improved.
3. The water side is combined, and a circulating pump, a deaerator and a water replenishing pump are arranged outside the critical area
The water side is combined, the two units share equipment such as a heat supply network circulating pump, a heat supply network deaerator and a heat supply network water replenishing pump, the equipment investment is reduced, meanwhile, the quick switching can be realized through the water side interconnection, and the heat supply reliability is improved. Arrange heat supply network circulating pump, heat supply network oxygen-eliminating device, heat supply network moisturizing pump etc. outside the vital area, can effectively solve the vital area and arrange closely, can't arrange the problem of many main equipment, the rational utilization space solves the problem of arranging.
4. Heat supply unit one-use one-standby scheme considering nuclear power overhaul period
The refueling overhaul period of the AP1000 nuclear power plant unit is 18 months, the overhaul period is about 1 month, and the adjustment of the refueling overhaul period brings the fuel consumption depth change of a reactor, thereby influencing the running cost of the unit, the arrangement of fuel assemblies after refueling and the like. When a plurality of units supply heat jointly, the unit overhaul working condition is inevitably generated in the heating season, as the nuclear power unit can usually provide larger heat supply load, a large heat source in a region is possible, a heat supply network usually needs to pay a large amount of cost to provide a standby heat source for the nuclear power unit, in order to effectively guarantee the heat supply reliability of a heat source side, a unit one-use one-standby scheme is adopted, a standby unit is reserved and overhauled in the heating season, and the heat supply reliability is guaranteed from the heat source side.
Drawings
Fig. 1 is a connection diagram of a multi-unit heating system of a nuclear power plant with a steam side unit system and a water side combined system provided by an embodiment.
Detailed Description
In order to make the invention more comprehensible, preferred embodiments are described in detail below with reference to the accompanying drawings.
Examples
As shown in fig. 1, a multi-unit heating system of a nuclear power plant with a steam-side unit system and a water-side combined system provided in this embodiment is provided, where the nuclear power plant includes more than 2 units with the same structure, each unit is provided with a primary circuit and two circuits, each unit includes a water-feeding pump 1 for conveying water in the two circuits to a steam generator 2, an outlet end of the steam generator 2 is sequentially connected to a high-pressure cylinder 3, a low-pressure cylinder 4, a condenser 5, and the water-feeding pump 1 to form a closed cycle, an output end of the low-pressure cylinder 4 is connected to a generator 6, and the low-pressure cylinder 4 is connected in parallel to a steam-side heat exchange pipeline in a steam-water heat exchanger 7; water side heat exchange pipelines in the steam-water heat exchangers 7 in all the units are connected in parallel and then connected with a heat supply network circulating pump 8 in a heat supply network circulating pump station C to form three loops, the heat supply network circulating pump 8 in the three loops is sequentially connected with a constant pressure pump 10 and a dirt remover 11 in series, and the constant pressure pump 10 is connected with a deaerator 9. The three loops and other loops at the downstream are respectively communicated with two heat exchange pipelines of the water-water heat exchanger 13 for heat exchange.
A valve a is arranged on a steam side heat exchange pipeline of a steam-water heat exchanger 7 in the unit, a valve b and a valve c are respectively arranged on a water side heat exchange pipeline, the valve a, the valve b and the valve c in the unit in normal operation are in an open state, and the valve a, the valve b and the valve c in the standby unit are in a closed state. Two sides of the three-loop water-feeding water heat exchanger 13 are respectively provided with a valve d and a valve e, when the three-loop water-feeding water heat exchanger operates normally, the valve d and the valve e are in an open state, and when the three-loop water-feeding water heat exchanger operates abnormally, the valve d and the valve e are in a closed state.
Water in the second loop of the nuclear power plant is boosted by the water feeding pump 1 and then conveyed to the steam generator 2, heat is absorbed in the steam generator 2 to be changed into saturated steam, the saturated steam sequentially enters the high-pressure cylinder 3 and the low-pressure cylinder 4 to do work to push the steam turbine to rotate, the steam turbine drives the generator 6 to generate electricity, the steam after doing work enters the condenser 5, heat is exchanged to seawater in the third loop, the seawater is condensed into water, and the water is conveyed to the steam generator 2 by the water feeding pump 1 after being heated step by step to complete closed circulation of the whole second loop. The invention extracts steam from the exhaust pipeline of the high-pressure cylinder 3 to heat the circulating water of the heat supply network, and the extracted steam is condensed and then recycled to the condenser 5, thereby realizing the water balance of the two loops. Each unit is provided with an independent heating network heater and a steam extraction drainage loop respectively, so that the steam sides are independent from each other, the units operate, each unit can meet the heat supply requirement when operating independently, a single unit supplies heat when operating normally, and the other unit is overhauled or reserved. Because the heater sets up around the unit, can realize the fast switch-over of heater, effectively shorten heat supply time of moving back, shorten hydrophobic pipeline length, directly utilize the pressure differential to drain, need not set up the drainage pump, save drainage pump investment and working costs. The investment is saved while the heat supply reliability is guaranteed.
The return water of the heat supply network circulating water in the water side heat exchange pipeline in the steam-water heat exchanger 7 firstly enters a heat supply network circulating pump station C, is filtered by a dirt separator 11, is subjected to pressure stabilization by a constant pressure pump 10, is boosted by a heat supply network circulating pump 8, is respectively conveyed to two units, and is heated in the steam-water heat exchanger 7 of the units to externally supply high-temperature circulating water.
And when the nuclear power plant is in normal operation, the steam-water heat exchanger 7 of any one of the two sets of the secondary circuit of the nuclear power plant operates, and the steam-water heat exchanger 7 of the other set does not operate for standby. The other unit can isolate the heat exchanger of the unit for standby by closing the steam side and water side isolation valves.
According to the invention, the water sides of the steam-water heat exchangers are communicated, and the water sides of the steam-water heat exchangers 7 of the two units run in parallel, so that the standby quick-cut operation can be effectively realized, meanwhile, 1/2 is saved in the investment of equipment such as a steam pipeline and a heat supply network circulating pump, the arrangement space in an important area is effectively saved by a water side combination scheme, and the equipment such as the heat supply network circulating pump, a deaerator and a constant pressure pump is arranged outside the important area, so that the reliability is improved and the investment is saved.
Claims (7)
1. A multi-unit heating system of a nuclear power plant with steam side unit system and water side combined system is characterized in that each unit comprises a water feeding pump (1) used for conveying water in two loops to a steam generator (2), the outlet end of the steam generator (2) is sequentially connected with a high pressure cylinder (3), a low pressure cylinder (4), a condenser (5) and the water feeding pump (1) to form closed circulation, the output end of the low pressure cylinder (4) is connected with a generator (6), and the low pressure cylinder (4) is connected with a steam side heat exchange pipeline in a steam-water heat exchanger (7) in parallel; water side heat exchange pipelines in the steam-water heat exchangers (7) in all the units are connected in parallel and then are connected with a heat supply network circulating pump (8) in a heat supply network circulating pump station (C) to form a loop.
2. The steam-side unit system and water-side combined system multi-unit heating system of the nuclear power plant as claimed in claim 1, wherein the heat supply network circulating pump (8) is connected with a constant pressure pump (10) and a dirt separator (11) in series in sequence, and the constant pressure pump (10) is connected with a deaerator (9).
3. The steam-side unit system and water-side combined system multi-unit heating system of the nuclear power plant as claimed in claim 1, wherein the three loops and other loops at the downstream are respectively communicated with two heat exchange pipelines of the water-water heat exchanger (13).
4. The multi-unit heating system of the nuclear power plant with steam side unit system and water side combined system as claimed in claim 1, wherein the water in the second loop of the nuclear power plant is boosted by the water feeding pump (1) and then is delivered to the steam generator (2), the heat absorbed in the steam generator (2) is changed into saturated steam, the saturated steam sequentially enters the high pressure cylinder (3) and the low pressure cylinder (4) to do work, the steam turbine drives the generator (6) to generate electricity, the steam after doing work enters the condenser (5), the heat is exchanged to the seawater in the third loop, and then is condensed into water, and the water is delivered to the steam generator (2) by the water feeding pump (1) after being heated step by step, so as to complete the closed cycle of the whole second loop; the return water of the circulating water of the heat supply network in the water side heat exchange pipeline in the steam-water heat exchanger (7) firstly enters a heat supply network circulating pump (8), is boosted by the heat supply network circulating pump (8) and is respectively conveyed to the two units, so that the heat supply requirements of the two units are met.
5. The steam side unit system and water side combined system multi-unit heating system of nuclear power plant according to claim 1, wherein in normal operation, the steam-water heat exchanger (7) in any unit of the nuclear power plant is operated, and other steam-water heat exchangers (7) are not operated and are standby.
6. The multi-unit heating system of the nuclear power plant with steam side unit system and water side combined system as claimed in claim 1, wherein a steam side heat exchange pipeline of a steam-water heat exchanger (7) in the unit is provided with a valve a, a water side heat exchange pipeline is provided with a valve b and a valve c respectively, the valve a, the valve b and the valve c in the unit in normal operation are in an open state, and the valve a, the valve b and the valve c in the spare unit are in a closed state.
7. The multi-unit heating system of the nuclear power plant with steam side unit system and water side combined system as claimed in claim 3, wherein a valve d and a valve e are respectively arranged on two sides of the three-loop water-feeding water heat exchanger (13), and when the three-loop water-feeding water heat exchanger is in normal operation, the valve d and the valve e are in an open state, and when the three-loop water-feeding water heat exchanger is not in normal operation, the valve d and the valve e are in a closed state.
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| Application Number | Priority Date | Filing Date | Title |
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| CN202010318895.9A CN111396156A (en) | 2020-04-21 | 2020-04-21 | Multi-unit heating system of nuclear power plant with steam side unit system and water side combined system |
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| Application Number | Priority Date | Filing Date | Title |
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| CN202010318895.9A CN111396156A (en) | 2020-04-21 | 2020-04-21 | Multi-unit heating system of nuclear power plant with steam side unit system and water side combined system |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113191093A (en) * | 2021-03-22 | 2021-07-30 | 国核电力规划设计研究院有限公司 | Pressurized water reactor two-loop steam-water flow model establishing method and multi-working-condition simulation method |
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2020
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113191093A (en) * | 2021-03-22 | 2021-07-30 | 国核电力规划设计研究院有限公司 | Pressurized water reactor two-loop steam-water flow model establishing method and multi-working-condition simulation method |
| CN113191093B (en) * | 2021-03-22 | 2024-02-06 | 国核电力规划设计研究院有限公司 | Pressurized water reactor two-loop steam-water flow model building method and multi-working-condition simulation method |
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