Pressurized water reactor heat storage power generation device
By installing a heat storage power generation device on the steam bypass pipeline of the pressurized water nuclear reactor, the problem of heat cannot be stored is solved, efficient storage and release of heat is achieved, the peak shaving capacity of nuclear power is improved, and the system operation cost is reduced.
Patent Information
- Application Number
- CN202422233665.9
- Authority / Receiving Office
- CN · China
- Patent Type
- Utility models(China)
- Current Assignee / Owner
- Filing Date
- 2024-09-11
- Publication Date
- 2025-08-01
- Estimated Expiration
- 2034-09-11
AI Technical Summary
The existing pressurized water nuclear reactor lacks heat storage and power generation devices, which leads to the inability to store heat, resulting in waste of resources, and the peak regulating depth is limited and the peak regulating flexibility is poor. It is unable to generate power through the storage and release of heat, affecting the peak regulating capacity of nuclear power.
A bypass branch line is set up on the steam bypass pipeline of the steam generator secondary side of the pressurized water nuclear reactor, and a heat storage and power generation device is installed, including multiple heat storage tanks and related equipment to realize the storage and release of heat, and optimize the power supply through "peak cutting and valley filling".
It realizes efficient storage and release of heat, avoids energy waste, improves the peak shaving capacity of nuclear power, reduces system operation costs, and meets large power demands.
Smart Images
Figure CN223177607U_ABST
Abstract
Description
Technical Field
[0001] The utility model relates to the technical field of nuclear energy application, in particular to a pressurized water reactor heat storage power generation device. Background Art
[0002] The statements in this section merely provide background technical information related to the present invention and do not necessarily constitute prior art.
[0003] Nuclear energy and renewable energy, as important components of non-fossil energy, play a vital role in building a clean, low-carbon, safe and efficient energy system and achieving the "dual carbon" goals.
[0004] Renewable energy, characterized by randomness, intermittency, and volatility, generates corresponding power fluctuations when connected to the grid. When renewable energy accounts for a small proportion of generation, traditional power sources can compensate for power fluctuations in real time. However, as the proportion of renewable energy generation increases, a mismatch between power supply and demand emerges. The resulting power fluctuations exceed the regulatory limits of traditional power sources, posing significant challenges to the safe, stable, and reliable operation of the grid and leading to widespread curtailment of solar and wind power.
[0005] Nuclear power has stable output, making it suitable for baseload electricity. It can provide essential support for power systems with a high proportion of renewable energy, thus facilitating the absorption of intermittent power sources such as wind and solar power. Generally, nuclear power units do not participate in grid peak regulation. They operate at low power only during special periods such as holidays or inclement weather, typically for no more than 15 days, for maintenance outages or power reductions. As renewable energy penetration increases in power grids, power systems with a high proportion of nuclear power face significant pressure to regulate grid peak loads, necessitating a more flexible approach for nuclear power.
[0006] Conventional nuclear power peak shaving methods. One method is, without changing the operating power of the reactor, to directly discharge steam into the condenser by means of a steam bypass turbine, reducing the output of the turbine, but causing a large amount of energy waste; or introducing the bypassed steam into other industrial fields for nuclear heating. However, due to the relatively low steam temperature parameters of the pressurized water reactor and the randomness of peak shaving for heating, the application range is limited and it cannot be fully utilized. Another method is to reduce the operating power of the reactor, resulting in a decrease in the amount of steam produced and thus a reduction in the output of the turbine. When changing the operating power of the reactor, due to the safety constraints of nuclear power units, the output of nuclear power units cannot change rapidly, and the peak shaving depth and ramp rate of nuclear power units need to be restricted. According to the nuclear load tracking requirements of pressurized water reactors, within 90% of the fuel cycle, with a step load change of ±10%, the ramp rate changes linearly at ±5% per minute. For example, in the "10 - 2 - 10 - 2" peak shaving mode, the nuclear power unit first operates at full load for 10 hours, then linearly reduces the unit output to 50% of the rated output of the unit within 2 hours, maintains this power stable for 10 hours, and then raises the unit output to full load within 2 hours for peak shaving. The frequent adjustment of the reactor power needs to be achieved by adjusting the rod position of the reactor control rods. Frequent rod position adjustment actions will bring adverse risks to the operation of the reactor and also cause stress fatigue of the equipment structural components. The above two peak shaving methods will cause a large amount of energy waste, waste nuclear fuel, and significantly increase the system operation cost; as the nuclear power peak shaving depth increases, its own peak shaving cost will also increase significantly, and the system operation cost will further increase with the increase in the nuclear power peak shaving depth.
[0007] Through the above analysis, it is found that there are certain problems in the existing technology:
[0008] The existing nuclear steam supply system of pressurized water nuclear reactors lacks a heat storage power generation device and cannot store heat, resulting in resource waste; during the nuclear power peak shaving process, the peak shaving depth is limited and the peak shaving flexibility is poor. It is impossible to generate electricity through the storage and release of heat, affecting the nuclear power peak shaving ability. Utility Model Content
[0009] Aiming at the problems existing in the existing technology, the present utility model provides a heat storage power generation device for a pressurized water reactor. By setting up the heat storage power generation device for a pressurized water reactor, heat storage power generation is realized. While achieving effective deep nuclear power peak shaving, it avoids a large amount of energy waste during the peak shaving process, improves the nuclear power peak shaving ability, and meets a large power demand.
[0010] In order to achieve the above object, the present utility model adopts the following technical solutions:
[0011] In the first aspect, a heat storage power generation device for a pressurized water reactor is disclosed, which is used for the nuclear steam supply system of a pressurized water nuclear reactor and includes:
[0012] On the steam bypass pipeline on the secondary side of the steam generator in the nuclear steam supply system of a pressurized water nuclear reactor, a bypass branch line is provided, and a heat storage power generation device is installed on the bypass branch line;
[0013] The heat storage power generation device includes: a first heat storage tank, a second heat storage tank, and a third heat storage tank;
[0014] The first heat storage tank, the second heat storage tank, and the third heat storage tank are connected in sequence.
[0015] As a further technical solution, the heat storage power generation device further includes a steam turbine of the heat storage power generation device, a condenser of the heat storage power generation device, and a feed water pump of the heat storage power generation device;
[0016] The first heat storage tank is connected to the steam turbine of the heat storage power generation device; the steam turbine of the heat storage power generation device is connected to the condenser of the heat storage power generation device; the condenser of the heat storage power generation device is connected to the feed water pump of the heat storage power generation device; the third heat storage tank is connected to the feed water pump of the heat storage power generation device.
[0017] As a further technical solution, the heat storage power generation device further includes a generator of the heat storage power generation device, and the generator of the heat storage power generation device is connected to the steam turbine of the heat storage power generation device.
[0018] As a further technical solution, heat storage media are provided in the first heat storage tank, the second heat storage tank, and the third heat storage tank.
[0019] As a further technical solution, heat exchange pipelines are provided in the first heat storage tank, the second heat storage tank, and the third heat storage tank.
[0020] As a further technical solution, the heat exchange pipelines all adopt serpentine tubes and are immersed in the heat storage media.
[0021] As a further technical solution, a number of valves are also provided on the bypass branch line.
[0022] As a further technical solution, the state parameters of the exhaust steam at the outlet of the steam turbine of the heat storage power generation device are 0.01 MPa and 46 °C.
[0023] As a further technical solution, the nuclear steam supply system of the pressurized water nuclear reactor includes a reactor and a main coolant pump, and the reactor, the steam generator, and the main coolant pump are connected in sequence to form the primary loop of the pressurized water nuclear reactor.
[0024] As a further technical solution, the nuclear steam supply system of the pressurized water nuclear reactor further includes a high-pressure cylinder of a steam turbine, a low-pressure cylinder of the steam turbine, a steam turbine separator reheater, a condenser, a condensate pump, a low-pressure heater, a deaerator, a feed water pump, and a high-pressure heater, forming a secondary loop of the steam cycle of the pressurized water reactor nuclear power generation unit.
[0025] One or more technical solutions of the present utility model have the following beneficial effects:
[0026] This embodiment provides a pressurized water reactor thermal energy storage power generation device, which arranges 3 thermal energy storage tanks and adopts a stepped heat exchange thermal energy storage method, realizing the storage and release of the heat of the pressurized water nuclear reactor, avoiding the waste of energy, and maximizing the heat recovery and utilization.
[0027] Based on the principle of minimally modifying the steam cycle system of the traditional pressurized water reactor power generation unit, on the steam bypass pipeline on the secondary side of the steam generator in the nuclear steam supply system of the pressurized water nuclear reactor, a bypass branch line is set, and a thermal energy storage power generation device is installed to realize the storage of thermal energy and the generation of electricity by releasing thermal energy; at the same time, based on this device, by adopting the method of "peak shaving and valley filling", the deficiencies such as limited peak regulation depth and poor peak regulation flexibility of nuclear power can be effectively compensated, and the operation cost of the system is greatly reduced. When the power demand is insufficient and the power production is excessive, the method of "peak shaving" is adopted to store the steam of the pressurized water reactor in the pressurized water reactor thermal energy storage power generation device in the form of thermal energy storage, and when the power demand is large and the power production is insufficient, the method of "valley filling" is adopted to release the thermal energy stored in the pressurized water reactor thermal energy storage power generation device for power generation to meet the large power demand.
[0028] The advantages of the additional aspects of the present utility model will be partly given in the following description, partly will become obvious from the following description, or will be understood through the practice of the present utility model. BRIEF DESCRIPTION OF THE DRAWINGS
[0029] The specification drawings constituting a part of the present utility model are used to provide a further understanding of the present utility model. The schematic embodiments of the present utility model and their descriptions are used to explain the present utility model and do not constitute an improper limitation of the present utility model.
[0030] Figure 1 It is a schematic diagram of the steam cycle system of the pressurized water nuclear reactor million-kilowatt power generation unit in this embodiment;
[0031] Figure 2 It is a schematic diagram of a nuclear steam supply system of a pressurized water nuclear reactor provided with a pressurized water reactor thermal energy storage power generation device in this embodiment;
[0032] Figure 3 It is a schematic diagram of a pressurized water reactor thermal energy storage power generation device in the embodiment;
[0033] In the figure: 1, pressurized water nuclear reactor; 2, steam generator; 3, primary coolant pump; 4, high-pressure cylinder of steam turbine; 5, first low-pressure cylinder of steam turbine; 6, second low-pressure cylinder of steam turbine; 7, third low-pressure cylinder of steam turbine; 8, generator; 9, moisture separator reheater; 10, condenser; 11, condensate pump; 12, first low-pressure heater; 13, second low-pressure heater; 14, third low-pressure heater; 15, fourth low-pressure heater; 16, deaerator; 17, feed water pump; 18, first high-pressure heater; 19, second high-pressure heater; 20, thermal energy storage power generation device; 21, first thermal energy storage tank; 22, second thermal energy storage tank; 23, third thermal energy storage tank; 24, steam turbine of thermal energy storage power generation device; 25, generator of thermal energy storage power generation device; 26, condenser of thermal energy storage power generation device; 27, feed water pump of thermal energy storage power generation device; 28, first valve; 29, second valve; 30, third valve; 31, fourth valve; 32, fifth valve; 33, sixth valve. Detailed implementation mode
[0034] It should be noted that the following detailed description is exemplary and is intended to provide further explanation of the present invention. Unless otherwise specified, all technical and scientific terms used herein have the same meaning as commonly understood by those of ordinary skill in the technical field to which the present invention belongs.
[0035] It should be noted that the terms used herein are only for describing the specific implementation mode and are not intended to limit the exemplary implementation mode according to the present invention.
[0036] Without conflict, the embodiments in the present invention and the features in the embodiments can be combined with each other.
[0037] Embodiment 1
[0038] With the increase in the penetration rate of renewable energy in the power grid system, in a power system with a relatively high proportion of nuclear power, the peak shaving pressure of the power grid is relatively large. For the existing nuclear power peak shaving methods, a large amount of energy waste and nuclear fuel waste will inevitably occur. At the same time, with the increase in the depth of nuclear power peak shaving, the operating cost of the system increases significantly. To solve these problems and meet the power demand, in the steam cycle system of a pressurized water nuclear reactor generator set, based on the principle of minimal modification, a bypass branch line is set on the steam turbine bypass pipeline of the existing pressurized water nuclear reactor, and a pressurized water reactor thermal energy storage power generation device is installed on this bypass branch line.
[0039] In this embodiment, a pressurized water reactor thermal energy storage power generation device for the nuclear steam supply system of a pressurized water nuclear reactor is provided, including:
[0040] A bypass branch line is set on the secondary side steam bypass pipeline of the steam generator in the nuclear steam supply system of the pressurized water nuclear reactor, and a thermal energy storage power generation device is installed on the bypass branch line.
[0041] In this embodiment, as Figure 1 shown, for the steam cycle system of a conventional pressurized water nuclear reactor million - kilowatt generating unit, taking a certain pressurized water nuclear reactor as an example, it mainly consists of a pressurized water reactor nuclear reactor 1, a steam generator 2, and a main coolant pump 3, etc., forming the primary loop of the pressurized water nuclear reactor, with a nuclear thermal power of 3415 MWt. The steam cycle secondary loop of the pressurized water reactor nuclear reactor generating unit is formed by the steam generator 2, the high - pressure cylinder 4 of the steam turbine, the first low - pressure cylinder 5 of the steam turbine, the second low - pressure cylinder 6 of the steam turbine, the third low - pressure cylinder 7 of the steam turbine, the moisture separator reheater 9, the condenser 10, the condensate pump 11, the first low - pressure heater 12, the second low - pressure heater 13, the third low - pressure heater 14, the fourth low - pressure heater 15, the deaerator 16, the feed water pump 17, the first high - pressure heater 18, and the second high - pressure heater 19.
[0042] In this implementation, as Figure 1 shown, the steam at the outlet of the steam generator has a steam pressure of 5.5 MPa and a temperature of 271 °C saturated steam, and is discharged from the steam generator at a speed of 1886 kg / s; 95% of the steam mass flow rate flows through the high - pressure cylinder 4 of the BC steam turbine, and the remaining 5% of the steam mass flow rate flows through BD for reheating the steam GI and HMJ discharged from the high - pressure cylinder 4 of the steam turbine. The extraction steam GI (pressure 1.05 MPa, dryness X = 0.88) from the high - pressure cylinder 4 of the steam turbine is used for high - pressure feed water heating IL and moisture separation steam reheating. After passing through the moisture separator reheater, the steam is reheated again to become steam at 0.95 MPa and 251 °C, flows through JK, enters the first low - pressure cylinder 5, the second low - pressure cylinder 6, and the third low - pressure cylinder 7 of the steam turbine to expand and do work, and becomes exhaust steam at 0.01 MPa and dryness X = 0.89, entering the condenser 10. In the low - pressure cylinder of the steam turbine, through the middle 4 - stage extraction steam, it flows through the first low - pressure heater 12, the second low - pressure heater 13, the third low - pressure heater 14, and the fourth low - pressure heater 15 for low - pressure feed water heating. After passing through the condenser, the water is unsaturated water, which is pressurized and heated step by step to become water at 3 MPa and 138 °C and enters the deaerator 16. Then, after being heated by the high - pressure heater, it flows through the steam generator 2 to form a cycle. Under the full - load operation condition, the net electric power base - load generating power is 1117 MWe, and the thermal efficiency is 31%.
[0043] In this embodiment, as Figure 2 shown, in order to achieve heat storage power generation in a pressurized water reactor, based on the steam cycle system of the nuclear power unit with minimal modification, a bypass branch line OPQRST is selected on the steam bypass line EF. A pressurized water reactor heat storage power generation device 20 is installed on this bypass branch line to store the thermal energy of the excess steam, and when the electricity demand peak occurs, the thermal energy is released in the form of steam to drive the steam turbine to do work and generate electricity.
[0044] In this embodiment, a bypass branch line may be provided on the steam turbine bypass pipeline of a pressurized water nuclear reactor in the steam cycle system of an already-operating power generation or newly-built pressurized water nuclear reactor generating unit, or in the steam cycle system of a pressurized water nuclear reactor generating unit under construction, and a pressurized water reactor thermal energy storage power generation device may be installed.
[0045] As Figure 2 、 Figure 3 shown, in this embodiment, the thermal energy storage power generation device includes: a first thermal energy storage tank 21, a second thermal energy storage tank 22, a third thermal energy storage tank 23, a thermal energy storage power generation device steam turbine 24, a thermal energy storage power generation device condenser 26, a thermal energy storage power generation device feed water pump 27, and a thermal energy storage power generation device generator 25.
[0046] The first thermal energy storage tank 21, the second thermal energy storage tank 22, and the third thermal energy storage tank 23 are connected in sequence; the first thermal energy storage tank 21 is connected to the thermal energy storage power generation device steam turbine 24; the thermal energy storage power generation device steam turbine 24 is connected to the thermal energy storage power generation device condenser 26; the thermal energy storage power generation device condenser 26 is connected to the thermal energy storage power generation device feed water pump 27; the third thermal energy storage tank 23 is connected to the thermal energy storage power generation device feed water pump 27, and the thermal energy storage power generation device generator 25 is connected to the thermal energy storage power generation device steam turbine 24.
[0047] In this embodiment, as Figure 2 、 Figure 3 shown, when there is an overproduction of electricity, the excess steam is introduced through the bypass branch line OPQ into the pressurized water reactor thermal energy storage power generation device. The steam flows through the first thermal energy storage tank 21, the second thermal energy storage tank 22, and the third thermal energy storage tank 23 in sequence, and releases thermal energy step by step according to the physical state parameters of the water vapor, storing it in the above three thermal energy storage tanks, and finally flowing through the RST branch line and through the condenser 10; then it is pressurized and heated again to become a cycle in the nuclear steam supply system.
[0048] In this embodiment, as Figure 2 、 Figure 3 shown, when the electricity demand is at a peak, the thermal energy stored in the above thermal energy storage tanks is released and converted into steam for power generation. The water in the thermal energy storage power generation device system flows through the third thermal energy storage tank 23, the second thermal energy storage tank 22, and the first thermal energy storage tank 21 in sequence, absorbs the thermal energy in the thermal energy storage tanks step by step according to the physical state parameters of the water, becomes superheated steam, flows through the thermal energy storage power generation device steam turbine 24 for expansion work, generates electricity through the thermal energy storage power generation device generator 25, the exhaust steam flows through the thermal energy storage device condenser 26, and then through the thermal energy storage power generation device feed water pump 27, and is pressurized and heated again to become a steam cycle in the thermal energy storage power generation system.
[0049] By adding a heat storage power generation device, a large amount of energy waste is avoided, and the maximum utilization of heat recovery is achieved. Through this heat storage method, the deficiencies such as the limited depth of nuclear power peak shaving and poor peak shaving flexibility can be effectively compensated, the nuclear power peak shaving capacity is improved, the system operation cost is reduced, and a large power demand can be met.
[0050] In this embodiment, as Figure 2 shown, several valves are also provided on the bypass line.
[0051] Specifically, on the steam bypass line EF, a bypass branch line OPQRST is set. On the bypass branch line OPQRST of the pressurized water reactor heat storage power generation device, there are also a first valve 28, a second valve 29, a third valve 30, a fourth valve 31, a fifth valve 32, and a sixth valve 33. Among them, the first valve 28, the second valve 29, the third valve 30, and the sixth valve 33 are used to adjust and control the steam flow for heat storage, and the second valve 29 and the fifth valve 32 are used to isolate the heat storage power generation device.
[0052] By setting the valves, it is possible to shunt to the bypass branch line proportionally according to the need of the peak shaving depth, adjust and control the steam flow in the heat storage device, and lay the foundation for the system to adopt the peak shaving and valley filling method; at the same time, it also plays a protective role for the heat storage device and avoids adverse effects.
[0053] In this embodiment, the heat storage media in the first heat storage tank 21, the second heat storage tank 22, and the third heat storage tank 23 can be heat-conducting oil media, such as silicone oil, mineral oil, synthetic oil, etc., which are suitable for heat storage media in the medium temperature range (100 - 400 °C); it can also be a molten salt medium of a non-eutectic mixture medium prepared in a certain proportion, such as adding other alkali metals or alkali metal cations, and a molten salt medium of 20% NaNO3 - 80% KNO3. By using the above heat storage media, heat storage can be better assisted.
[0054] In this embodiment, as Figure 3 shown, heat exchange pipelines are provided in the first heat storage tank 21, the second heat storage tank 22, and the third heat storage tank 23, all in the form of serpentine tubes and immersed in the heat storage media of the heat storage tanks. The heat exchange pipelines are divided into heat exchange pipelines for peak shaving steam heat storage and heat exchange pipelines for valley filling heat release power generation. That is, the function of the heat exchange pipelines is for heat exchange during peak shaving steam heat storage or valley filling heat release.
[0055] In this embodiment, as Figure 2 、 Figure 3 shown, based on the pressurized water reactor heat storage power generation device, nuclear power peak shaving adopts the "peak shaving and valley filling" method to meet the power demand.
[0056] Specifically, during peak shaving steam thermal energy storage, by adjusting the valve opening and closing states, the steam on the secondary side of the steam generator is proportionally diverted into the bypass branch according to the requirements of the peak shaving depth and is used in the thermal energy storage power generation device for steam thermal energy storage. When the physical state parameters of the steam on the secondary side of the steam generator 2 at point U1 are saturated steam at 271°C, 5.5 MPa, and dryness X = 1, it first enters the first thermal energy storage tank 21 for the first-stage thermal energy storage. After the steam is stored, it becomes wet steam, that is, the physical state parameters at point V1 are wet steam at 271°C, 5.5 MPa, and 0 < χ < 1. Then, the wet steam enters the second thermal energy storage tank 22 for the second-stage thermal energy storage. After the steam is stored, it becomes liquid saturated water, that is, the physical state parameters at point W1 are liquid saturated water at 271°C, 5.5 MPa, and dryness χ = 0. Finally, the liquid water enters the third thermal energy storage tank 23 for the third-stage thermal energy storage and becomes liquid water, that is, the physical state parameters at point X1 are liquid water at 46°C, 5.5 MPa, completing the steam thermal energy storage process. The liquid water after heat exchange enters the condenser 10 to release heat further and then is pressurized for circulation.
[0057] In this embodiment, during peak shaving steam thermal energy storage, it is a stable isobaric thermal process. Compared with the base load operation of the nuclear power plant, thermal energy storage is carried out at a power of 119 MW within 4 hours. The peak shaving power demand time is 4 - 5 hours and increases to 9 hours in summer.
[0058] Based on the pressurized water reactor thermal energy storage power generation device, through the above steps, when the power demand is insufficient and the power is in excess, the "peak shaving" method is adopted to store the steam of the pressurized water reactor by thermal energy storage, avoiding a large amount of waste of energy during the peak shaving process, making effective use of nuclear fuel, reducing the operation cost, and laying a foundation for meeting a larger power demand.
[0059] During valley filling heat release power generation, first, the liquid water at 25°C at point X2 in the pipeline system of the thermal energy storage power generation device enters the third thermal energy storage tank 23, and the liquid water is heated by the thermal energy released by the thermal energy storage tank. At point W2, it becomes liquid saturated water with dryness χ = 0. Then, the liquid saturated water enters the second thermal energy storage tank 22, and the liquid saturated water is heated by the thermal energy released by the thermal energy storage tank. At point V2, it becomes saturated steam with dryness X = 1. Finally, the saturated steam enters the first thermal energy storage tank 21, and the saturated steam is heated by the heat released by the thermal energy storage tank. At point U2, it becomes superheated steam with dryness X > 1. The superheated steam with dryness X > 1, whose temperature range is 120 - 251°C and steam pressure range is 0.2 - 4.04 MPa, flows through the steam turbine 24 of the thermal energy storage power generation device to do work and generate electricity, and then enters the condenser 26 of the thermal energy storage power generation device, and further completes the thermal energy power generation cycle through auxiliary equipment such as the feed water pump 27 of the thermal energy storage power generation device.
[0060] Among them, the temperature T at point U2U2 , needs to be greater than the saturation temperature of 0.2MPa and less than the temperature T of U1 U1 , the maximum temperature difference is no more than 20℃.
[0061] Based on the pressurized water reactor heat storage power generation device, after the above steps, when the power demand is large and the power production is insufficient, the "valley filling" method is adopted to release the stored heat to generate electricity to meet the large power demand.
[0062] In this embodiment, when the valley is filled with thermal power generation, the thermal power generation quality fraction is the ratio of the actual thermal power generation steam mass flow rate to its mass flow rate under the design conditions, and the thermal power generation quality fraction is 0.3≤F D Varies within the range of ≤1.
[0063] In the case of valley-filling heat release power generation, in order to avoid erosion and corrosion of the blades in the steam turbine 24 of the heat storage power generation device, the steam quality at the last stage outlet is χ>0.88.
[0064] The state of the exhaust steam at the outlet of the steam turbine 24 of the thermal storage power generation device is 0.01 MPa and 46°C.
[0065] When using valley-filling thermal power generation, the calculation process of thermal efficiency is as follows:
[0066] The isentropic efficiency η of the water pump 27 using the heat storage power generation device p , calculate the enthalpy at the outlet of the water pump 27 of the thermal storage power generation device, η p =(h as -h i ) / (h o -h l ), where h o is the enthalpy at the pump outlet, h 0.3 is the isentropic enthalpy at the pump outlet, h l is the enthalpy at the pump inlet.
[0067] In this embodiment, the mass flow rate under the design conditions of the thermal storage power generation device is used. The actual inlet pressure P of the water pump 27 of the thermal storage power generation device i and actual outlet pressure P o , and the inlet pressure P under design conditions Lref and outlet pressure under design conditions Calculating the mass flow rate of thermal storage power generation devices According to the formula Calculated.
[0068] In this embodiment, according to the isentropic efficiency η of the steam turbine 24 of the thermal storage power generation device s , calculate the enthalpy at the turbine outlet, according to the formula Calculated, where h ois the enthalpy at the outlet of the steam turbine, h 0.3 is the isentropic enthalpy at the outlet of the steam turbine, h i is the enthalpy at the inlet of the steam turbine.
[0069] Specifically, the isentropic efficiency η of the steam turbine 24 of the heat storage power generation device s increases with the increase of the mass flow rate, wherein, is the isentropic efficiency under design conditions, is the mass flow rate, is the mass flow rate under design conditions.
[0070] The mass flow rate under design conditions is also F D = the mass flow rate when 1, and can be calculated according to the formula, where is the maximum heat release mechanical work, is the base load work under design conditions.
[0071] The total heat storage energy under design conditions is where t D is the heat storage time.
[0072] For example, the heat storage of saturated steam at 5.5 MPa and 271 °C is 2.1 GWht. When filling valleys and releasing heat for power generation, the steam at the inlet of the steam turbine 24 of the heat storage power generation device is superheated steam at 251 °C and 1.14 MPa, and its heat release efficiency is 0.23.
[0073] The above are only the preferred embodiments of the present invention and are not used to limit the present invention. For those skilled in the art, the present invention can have various changes and modifications. Any modification, equivalent replacement, improvement, etc. made within the spirit and principle of the present invention shall be included in the protection scope of the present invention.
Claims
1. A heat storage power generation device for a pressurized water reactor, which is used for the nuclear steam supply system of a pressurized water nuclear reactor, and is characterized in that Comprising: On the steam bypass pipeline of the secondary side of the steam generator in the nuclear steam supply system of a pressurized water nuclear reactor, a bypass branch line is provided, and a heat storage power generation device is installed on the bypass branch line; The heat storage power generation device includes: a first heat storage tank, a second heat storage tank, and a third heat storage tank; The first heat storage tank, the second heat storage tank, and the third heat storage tank are connected in sequence.
2. A pressurized water reactor thermal energy storage power generation device according to claim 1, characterized in that, The heat storage power generation device further includes a heat storage power generation device steam turbine, a heat storage power generation device condenser, and a heat storage power generation device feed water pump; The first heat storage tank is connected to the heat storage power generation device steam turbine; the heat storage power generation device steam turbine is connected to the heat storage power generation device condenser; the heat storage power generation device condenser is connected to the heat storage power generation device feed water pump; the third heat storage tank is connected to the heat storage power generation device feed water pump.
3. A pressurized water reactor thermal energy storage power generation device according to claim 1, characterized in that, The heat storage power generation device further includes a heat storage power generation device generator, and the heat storage power generation device generator is connected to the heat storage power generation device steam turbine.
4. A pressurized water reactor heat storage power generation device according to claim 1, characterized in that, The first heat storage tank, the second heat storage tank, and the third heat storage tank are all provided with heat storage media.
5. The pressurized water reactor thermal energy storage power generation device according to claim 4, characterized in that, Heat exchange pipelines are provided in the first heat storage tank, the second heat storage tank, and the third heat storage tank.
6. The pressurized water reactor heat storage power generation device according to claim 5, wherein The heat exchange pipelines all adopt serpentine tubes and are immersed in the heat storage media.
7. A pressurized water reactor thermal energy storage power generation device according to claim 1, characterized in that, A number of valves are also provided on the bypass branch line.
8. A pressurized water reactor thermal energy storage power generation device according to claim 2, characterized in that, The state parameters of the exhaust steam at the outlet of the heat storage power generation device steam turbine are 0.01 MPa and 46 °C.
9. The pressurized water reactor thermal energy storage power generation device according to claim 1, characterized in that, The nuclear steam supply system of the pressurized water nuclear reactor further includes a reactor and a primary coolant pump. The reactor, the steam generator, and the primary coolant pump are connected in sequence to form the primary loop of the pressurized water nuclear reactor.
10. A pressurized water reactor thermal energy storage power generation device according to claim 1, characterized in that, The nuclear steam supply system of the pressurized water nuclear reactor further includes a high-pressure cylinder of the steam turbine, a low-pressure cylinder of the steam turbine, a steam turbine separator reheater, a condenser, a condensate pump, a low-pressure heater, a deaerator, a feed water pump, and a high-pressure heater to form the steam cycle secondary loop of the pressurized water reactor nuclear power generation unit.