CN214370112U

CN214370112U - Nuclear power station two-loop thermodynamic system

Info

Publication number: CN214370112U
Application number: CN202023000589.5U
Authority: CN
Inventors: 赵清森; 张鼎; 任天翔; 王加勇; 邓德兵; 陈伟; 杨杰
Original assignee: China General Nuclear Power Corp; CGN Power Co Ltd; Suzhou Nuclear Power Research Institute Co Ltd
Current assignee: China General Nuclear Power Corp; CGN Power Co Ltd; Suzhou Nuclear Power Research Institute Co Ltd
Priority date: 2020-12-15
Filing date: 2020-12-15
Publication date: 2021-10-08
Anticipated expiration: 2030-12-15

Abstract

The utility model relates to a two-loop thermodynamic system of a nuclear power station, which comprises a heat exchange pipeline connected between a condenser and an evaporator, a low-pressure heat recovery system for heating condensed water in the heat exchange pipeline, a high-pressure heat recovery system and a deaerator, and also comprises a heating system, wherein the heating system comprises a heat generating device and a heat collecting and exchanging device for heating the condensed water in the heat exchange pipeline by the heat generated by the heat generating device; the utility model discloses an utilize solar energy heating nuclear power station feedwater, under the prerequisite without the help of external energy, reduce the use of two return circuits thermodynamic system of nuclear power station to the extraction of steam, especially improve main steam work quality in summer, finally improve power station generating power, solar energy provides new mode for follow-up optimization nuclear power safe operation in the application of nuclear power station simultaneously.

Description

Nuclear power station two-loop thermodynamic system

Technical Field

The utility model relates to a solar photothermal utilization field, nuclear power field, concretely relates to two return circuits thermodynamic system of nuclear power station.

Background

At present, a secondary loop thermodynamic system of a nuclear power station heats the feed water temperature by extracting working steam in a steam turbine, so that the overall thermal efficiency of the nuclear power station is improved. The two-loop thermodynamic system comprises a low-pressure heat regenerative system, a deaerator and a high-pressure heat regenerative system, after a steam turbine works, condensed water generated by the condenser is heated by the low-pressure heat regenerative system, enters the deaerator for high-temperature deaerating, is further heated by the high-pressure heat regenerative system, and then enters a boiler (the boiler generates steam and then supplies the steam to the steam turbine again for power generation).

Solar energy is an inexhaustible clean energy, and in today with increasingly severe environmental and energy problems, many countries have studied and practiced solar power generation technology and achieved some achievements. Solar photo-thermal power generation is also called focusing solar photo-thermal power generation, can utilize solar energy on a large scale, and is an effective way for solving the energy problem. The solar radiation energy is collected by an optical system and is used for heating a working medium to generate high-temperature steam to drive a steam turbine set to generate power. Solar photo-thermal power generation is an effective mode for utilizing solar energy, and currently, the solar photo-thermal power generation mainly comprises a plurality of typical solar power generation modes such as a groove type solar power generation mode, a tower type solar power generation mode, a linear Fresnel type solar power generation mode and a disc type solar power generation mode. Due to the intermittency and the fluctuation of solar energy resources, the simple Fresnel type thermal power generation system has the problems of unstable output power and the like. To realize stable and continuous operation, a heat storage device is generally required, but the addition of the heat storage device can increase the manufacturing cost of the solar thermal power generation system.

The solar nuclear power generating set is also used as clean energy, the power generating principle is similar, and how to complement the solar energy and the nuclear energy to improve the generating efficiency of the nuclear power generating set in summer is a small challenge.

Disclosure of Invention

The utility model aims at overcoming the not enough of prior art and providing a nuclear power station two return circuits thermodynamic system.

In order to achieve the above purpose, the utility model adopts the technical scheme that:

the utility model provides a two return circuits thermodynamic system of nuclear power station, two return circuits thermodynamic system is including connecting the heat transfer pipeline between condenser and evaporimeter, carry out the low pressure backheat system that heats to the condensate water in the heat transfer pipeline, high pressure backheat system, the oxygen-eliminating device, the low pressure backheat system includes the low pressure jar, locate No. 1 low pressure feed water heater on the heat transfer pipeline, No. 2 low pressure feed water heater, No. 3 low pressure feed water heater, No. 4 low pressure feed water heater, the high pressure backheat system includes the high pressure jar, locate No. 6 high pressure feed water heater on the heat transfer pipeline, No. 7 high pressure feed water heater, its characterized in that: the two-loop thermodynamic system also comprises a heating system, wherein the heating system comprises a heat generating device and a heat collecting and exchanging device which heats the condensed water in the heat exchanging pipeline by the heat generated by the heat generating device.

Preferably, the heat generating device is a solar photo-thermal device.

Preferably, the solar photothermal device comprises a linear fresnel reflective concentrating system.

Preferably, the heating system further comprises a heating pipeline, two ends of the heating pipeline are respectively communicated with the heat exchange pipeline, and the heat collection and exchange device is arranged on the heating pipeline.

Preferably, the heating system further comprises a bypass pipeline, two ends of which are respectively communicated with the heat exchange pipeline, and the bypass pipeline is connected with the heating pipeline in parallel.

Preferably, the heat collection and exchange device is arranged at the downstream of any one of No. 1 low-pressure heater, No. 2 low-pressure heater, No. 3 low-pressure heater, No. 4 low-pressure heater, No. 6 high-pressure heater and No. 7 high-pressure heater.

Preferably, the heat collection and exchange device is arranged at the downstream of the No. 4 low-pressure heater.

Preferably, the heat collection and exchange device is arranged at the downstream of the No. 7 high-pressure heater.

Preferably, the bypass conduit is provided with a first switching valve.

Preferably, two second switching valves are arranged on the heating pipeline, and the two second switching valves are respectively positioned at the upstream and the downstream of the heat collecting and exchanging device.

Due to the implementation of the above technical scheme, compared with the prior art, the utility model have the following advantage:

the utility model discloses an utilize solar energy heating nuclear power station feedwater, under the prerequisite without the help of external energy, reduce the use of two return circuits thermodynamic system of nuclear power station to the extraction of steam, especially improve main steam work quality in summer, finally improve power station generating power, solar energy provides new mode for follow-up optimization nuclear power safe operation in the application of nuclear power station simultaneously.

Drawings

Fig. 1 is a schematic view of the overall layout of the two-circuit thermodynamic system of the present invention (the heat collecting and exchanging device is disposed at the outlet of the low-pressure heat regenerative system);

FIG. 2 is a schematic view of the overall layout of the two-circuit thermodynamic system of the present invention (the heat collecting and exchanging device is disposed at the outlet of the high-pressure heat recovery system);

wherein: 100. a condenser; 200. an evaporator; 300. a heat exchange conduit; 40. a deaerator; 50. a linear Fresnel reflection light-condensing system; 51. a heat collection and exchange device; g1, low pressure cylinder; g2, high pressure cylinder; j1, low pressure heater No. 1; j2, low pressure heater No. 2; j3, low pressure heater No. 3; j4, low pressure heater No. 4; j6, high pressure heater No. 6; j7, high pressure heater No. 7; d1, a bypass line; d2, heating the pipeline; f1, a first switching valve; f2, and a second switching valve.

Detailed Description

The present invention will be described in further detail with reference to the accompanying drawings and specific embodiments.

As shown in fig. 1 and 2, the two-loop thermodynamic system of the nuclear power plant includes a heat exchange pipe 300 connected between a condenser 100 and an evaporator 200, a low-pressure regenerative system for heating condensed water in the heat exchange pipe 300, a high-pressure regenerative system, and a deaerator 40, the low-pressure regenerative system includes a low-pressure cylinder g1, a No. 1 low-pressure heater j1, a No. 2 low-pressure heater j2, a No. 3 low-pressure heater j3, and a No. 4 low-pressure heater j4 which are disposed on the heat exchange pipe 300, the high-pressure regenerative system includes a high-pressure cylinder g2, a No. 6 high-pressure heater j6 and a No. 7 high-pressure heater j7 which are disposed on the heat exchange pipe 300, and the two-loop thermodynamic system further includes a heating system which includes a heat generating device and a heat collecting and exchanging device 51 for heating the condensed water in the heat exchange pipe 300 by the heat generated by the heat generating device.

The heat generating device is a solar photo-thermal device. The solar photothermal device includes a linear fresnel reflective concentrating system 50. By utilizing the unique characteristics of the solar photothermal technology, the reflecting mirror group of the linear Fresnel reflection condensing system 50 is arranged on the factory area of the nuclear power station or the roof of a steam turbine machine room, the energy gathered by the solar photothermal device is directly used for heating the water supply of the two-loop thermodynamic system of the nuclear power station through the heat collection and exchange device 51, the water supply temperature is increased, the steam is pumped by the steam turbine regenerative system, the pumped steam is returned to the steam turbine for continuous work, and the heat efficiency and the economical efficiency of the nuclear power station are improved.

In order to improve the light and heat collecting efficiency, the reflecting condenser mirror surface is designed to be a secondary song surface type with the light condensing characteristic, and the optical light condensing efficiency is more than or equal to 90 percent. The surface coating of the heat collection and exchange device 51 is an improvement of a solar selective absorption coating, can resist the high temperature of 300 ℃, and has the absorption rate of over 96 percent in the solar spectrum range.

Furthermore, the utility model discloses a unipolar automatic tracking system makes linear fei nieer reflection condensing system 50 in the season of difference, and the sunshine time of difference can both be the collection solar radiation energy of maximum efficiency, and control mode is optional predetermines process control or photoelectric sensing control. The preset process control is to calculate the position and angle of the reflector according to the solar operation rule and control the rotation of the mirror shaft through the movement of the mechanical mechanism. The photoelectric sensing control is that the photoelectric sensor instantly collects and measures the sunlight direction, and the mechanical mechanism is controlled to move after the sunlight direction is processed by a circuit. The disadvantage of the photoelectric sensing control mode is that the correct position of the sun cannot be found in cloudy or rainy days, and manual intervention and adjustment are needed.

The heat collection and heat exchange device 51 can be arranged at the downstream of any one of the low-pressure heater j1 No. 1, the low-pressure heater j2 No. 2, the low-pressure heater j3 No. 3, the low-pressure heater j4 No. 4, the high-pressure heater j6 No. 6 and the high-pressure heater j7 No. 7, and the heating efficiency of the heat collection and heat exchange device 51 is higher as the heat collection and heat exchange device is closer to the outlet of the heat exchange pipeline 300; in this embodiment, due to the limitation of the field space of the existing two-circuit regenerative system, the heat collecting and exchanging device 51 is preferably disposed downstream of the No. 4 low-pressure heater j4 or downstream of the No. 7 high-pressure heater j7 without being greatly modified on the field.

If the heating system heats the final water supply temperature of the two-loop regenerative system (downstream of the No. 7 high-pressure heater j 7), the yield is the highest, the steam extraction amount of the low-pressure heater, the deaerator 40 and the high-pressure heater is reduced, or the low-pressure heater, the deaerator 40 and the high-pressure heater are not used for heating at all, and the use of steam extraction is also avoided. If the heating system is used for heating condensed water at the outlet of the low-pressure heater (the downstream of the No. 4 low-pressure heater j4 (the upstream of the deaerator 40), the steam extraction amount of the deaerator 40 and the high-pressure heater is reduced, the extracted steam of the exhaust heat recovery system returns to the steam turbine to continue acting, the power and the heat efficiency of the unit are improved, the comprehensive efficiency is lower than that of a mode for heating the outlet temperature of the high-pressure heater in the mode, automatic control is easy to realize, and the potential safety hazard caused by the fact that the final water supply temperature is over-poor can be avoided.

The heating system further comprises a heating pipeline d2 with two ends respectively communicated with the heat exchange pipeline 300, and the heat collection and exchange device 51 is arranged on the heating pipeline d 2. In addition, the heating system further includes a bypass pipe d1 having both ends respectively communicated with the heat exchange pipe 300, and the bypass pipe d1 is disposed in parallel with the heating pipe d 2. The bypass pipeline d1 is provided with a first switching valve f 1; two second switching valves f2 are arranged on the heating pipeline d2, and the two second switching valves f2 are respectively positioned at the upstream and the downstream of the heat collecting and exchanging device 51.

The utility model discloses some circumstances when nuclear power station two return circuits thermodynamic system uses as follows: when the linear fresnel reflection concentrating system 50 is capable of receiving solar radiation energy (e.g., during the day), the first switching valve f1 is closed and the second switching valve f2 is opened, or both the first switching valve f1 and the second switching valve f2 are opened; when the linear fresnel reflection concentrating system 50 is unable to receive solar radiation energy (e.g., at night), the first switching valve f1 is opened and the second switching valve f2 is closed.

The final feed water temperature control deviation of a nuclear power plant M310 unit commonly used in China is 226 +/-2.5 ℃, the control deviation needs to be switched and used through a bypass pipeline d1 and a heating pipeline d2, and the maximum deviation is always controlled not to exceed 2.5 ℃ under the condition of solar radiation energy change, so that the operation safety of key equipment of the nuclear power plant is guaranteed.

The bypass pipe d1 is used for shunting the flow of the condensed water of the heat collection and heat exchange device 51 during heat exchange, and also controlling the water outlet temperature of the heat exchange pipe 300, so that the feed water discharged from the heating pipe d2 after heat exchange of the heat collection and heat exchange device 51 is prevented from vaporizing by mixing cold water and hot water. In addition, the distance between the final feed water temperature of the nuclear power station and a design value is not more than 2.5 ℃ at most, and the thermal power of a heating thermal system is not more than 17MW at most according to thermal balance calculation. According to a conservative concept in the nuclear power field, 10% of safety allowance is designed, so that the maximum designed thermal power of the heating system does not exceed 15 MW; the thermal power of the heating system is actually determined according to the temperature and the pressure of the condensed water at the outlet of the heater, so that the condensed water is prevented from being vaporized to cause equipment damage.

To sum up, the utility model discloses an utilize solar energy heating nuclear power station feedwater, under the prerequisite not with the help of external energy, reduce the use of two return circuits thermodynamic system of nuclear power station to the extraction of steam, especially improve the main steam work quality in summer, finally improve power station generating power, solar energy provides new mode for follow-up optimization nuclear power safe operation in the application of nuclear power station simultaneously.

The above embodiments are only for illustrating the technical concept and features of the present invention, and the purpose thereof is to enable those skilled in the art to understand the contents of the present invention and to implement the present invention, so as not to limit the protection scope of the present invention, and all equivalent changes or modifications made according to the spirit of the present invention should be covered by the protection scope of the present invention.

Claims

1. The utility model provides a two return circuits thermodynamic system of nuclear power station, two return circuits thermodynamic system is including connecting the heat transfer pipeline between condenser and evaporimeter, the low pressure backheat system, high pressure backheat system, the oxygen-eliminating device that heat is carried out to the condensate water in the heat transfer pipeline, the low pressure backheat system include the low pressure jar, locate No. 1 low pressure heater, No. 2 low pressure heater, No. 3 low pressure heater, No. 4 low pressure heater on the heat transfer pipeline, the high pressure backheat system include the high pressure jar, locate No. 6 high pressure heater, No. 7 high pressure heater on the heat transfer pipeline, its characterized in that: the two-loop thermodynamic system further comprises a heating system, wherein the heating system comprises a heat generating device and a heat collecting and exchanging device which heats the condensed water in the heat exchanging pipeline by using the heat generated by the heat generating device.

2. The nuclear power plant two-circuit thermodynamic system of claim 1, wherein: the heat generating device is a solar photo-thermal device.

3. The nuclear power plant two-circuit thermodynamic system of claim 2, wherein: the solar photo-thermal device comprises a linear Fresnel reflection light-gathering system.

4. The nuclear power plant two-circuit thermodynamic system of claim 1, wherein: the heating system further comprises a heating pipeline, two end parts of the heating pipeline are respectively communicated with the heat exchange pipeline, and the heat collection and exchange device is arranged on the heating pipeline.

5. The nuclear power plant two-circuit thermodynamic system of claim 4, wherein: the heating system further comprises a bypass pipeline, two end parts of the bypass pipeline are respectively communicated with the heat exchange pipeline, and the bypass pipeline is connected with the heating pipeline in parallel.

6. The nuclear power plant two-circuit thermodynamic system of claim 1, wherein: the heat collection and exchange device is arranged at the downstream of any one of the No. 1 low-pressure heater, the No. 2 low-pressure heater, the No. 3 low-pressure heater, the No. 4 low-pressure heater, the No. 6 high-pressure heater and the No. 7 high-pressure heater.

7. The nuclear power plant two-circuit thermodynamic system of claim 1, wherein: the heat collection and exchange device is arranged at the downstream of the No. 4 low-pressure heater.

8. The nuclear power plant two-circuit thermodynamic system of claim 1, wherein: the heat collection and exchange device is arranged at the downstream of the No. 7 high-pressure heater.

9. The nuclear power plant two-circuit thermodynamic system of claim 5, wherein: the bypass pipeline is provided with a first switching valve.

10. The nuclear power plant two-circuit thermodynamic system of claim 9, wherein: and two second switching valves are arranged on the heating pipeline and are respectively positioned at the upstream and the downstream of the heat collection and exchange device.