A nuclear power steam-driven auxiliary feedwater pump and related system drain recovery device
By designing a hydrophobic auxiliary water supply pump and related systems for nuclear power, and using pneumatic hydrophobic pumps and overflow pipeline design, the problem of water phobic in the existing technology cannot be recovered, and efficient utilization of resources and stable operation of the system are achieved.
Patent Information
- Application Number
- CN202110270777.X
- Authority / Receiving Office
- CN · China
- Patent Type
- Patents(China)
- Current Assignee / Owner
- Filing Date
- 2021-03-12
- Publication Date
- 2025-02-14
- Estimated Expiration
- 2041-03-12
AI Technical Summary
The existing nuclear power steam auxiliary water supply pump cannot effectively recover water-breathing, resulting in waste of resources and loss of the second circuit thermal energy.
A hydrophobic recovery device for nuclear power steam auxiliary water supply pump and related systems was designed, and the hydrophobic recovery pump was used to intermittently recover the hydrophobic, and the closed loop and stability of the system were ensured through overflow pipeline design and water sealing mechanism.
Continuous recovery of hydrophobic water is achieved, resource waste is avoided, closed loop of the second loop system is ensured, and the steam assisted water supply pump is prevented from being unavailable in the event of a failure.
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Figure CN115076151B_ABST
Abstract
Description
Technical Field
[0001] The present invention belongs to process design and equipment, and in particular relates to a nuclear power steam-driven auxiliary feedwater pump and a related system drain recovery device. Background Art
[0002] The nuclear power steam-driven auxiliary feedwater pump needs to be in hot standby status daily. Its shaft seal water is deoxygenated water, which needs to be continuously supplied and consumed. In addition, the amount of condensate in the steam supply and exhaust pipelines is also very considerable. The existing steam-driven auxiliary feedwater pump discharges it to the drainage system without recycling it, which results in huge waste and increases the preparation work of deoxygenated water and the loss of heat energy in the secondary circuit. Summary of the invention
[0003] The purpose of the present invention is to provide a nuclear power steam-driven auxiliary feedwater pump and a related system drain recovery device, which can continuously collect drain and recover it to the condenser, avoiding huge waste and ensuring the closed loop of this section of the secondary circuit system.
[0004] The technical solution of the present invention is as follows: a nuclear power steam-driven auxiliary water supply pump, including a pump body, a pump cover, a gasket, an exhaust valve assembly, an intake valve assembly, an inlet check valve, an outlet check valve, a linkage mechanism assembly, a drain valve assembly, a lever mechanism assembly, a float assembly and a liquid level gauge assembly, a liquid level gauge assembly is installed on one side of the outside of the pump body, one side of the pump body is connected to the pump cover, an exhaust valve assembly and an inlet valve assembly are respectively arranged on the upper part of the pump cover, the exhaust valve assembly is connected to the linkage mechanism assembly, the linkage mechanism assembly is connected to the lever mechanism assembly, the lever mechanism assembly is connected to the float assembly, a water outlet check valve is arranged at the lower part of the outer side of the pump cover, a drain valve assembly is also arranged at the lower part of the pump cover, and an inlet check valve is connected to the middle of the pump cover.
[0005] One end of the liquid level gauge assembly is located at the lower part of the pump body.
[0006] One end of the liquid level gauge assembly is located at the upper part of the pump body.
[0007] The pump body and pump cover of the liquid level meter assembly are provided with gaskets.
[0008] A nuclear power steam-driven auxiliary feedwater pump and a related system drain recovery device, including a steam pipeline drain exhaust device, a steam-water separator, a compressed air storage, a drainage system, a pneumatic drain pump, a filter and a condenser. The steam pipeline drain exhaust device is connected to the steam-water separator, the steam-water separator is respectively connected to the drainage system and the pneumatic drain pump, the pneumatic drain pump is connected to the compressed air storage, the pneumatic drain pump is connected to the filter, and the filter is connected to the condenser.
[0009] The steam-water separator is communicated with the exhaust port.
[0010] The pneumatic drain pump is connected to the exhaust port.
[0011] The beneficial effects of the present invention are: 1) the continuous drainage from the upstream can be intermittently recovered to the condenser through the pneumatic drain pump; 2) during the intermittent stage of the drain pump, the downstream water seal can prevent the back suction caused by the negative pressure of the condenser; 3) the design of the overflow pipeline can not only ensure that there is no overflow when the drain pump is operating normally, but also ensure the normal drainage of the upstream during the shutdown or maintenance isolation of the drain pump. The latter function is particularly important, which can prevent the unavailability of the pneumatic auxiliary water supply pump due to poor drainage; 4) the internal structure of the pneumatic drain pump can mechanically interlock the trigger switch inlet / drain valve, as well as the inlet and outlet valves of compressed air, saving gas consumption. BRIEF DESCRIPTION OF THE DRAWINGS
[0012] Figure 1 A schematic diagram of the structure of a nuclear power steam-driven auxiliary feedwater pump provided by the present invention;
[0013] Figure 2 The present invention provides a schematic diagram of a nuclear power steam-driven auxiliary feedwater pump and a related system water recovery device.
[0014] In the figure, 1 is a pump body, 2 is a pump cover, 3 is a gasket, 4 is an exhaust valve assembly, 5 is an air inlet valve assembly, 6 is a water inlet check valve, 7 is a water outlet check valve, 8 is a linkage mechanism assembly, 9 is a steam trap assembly, 10 is a lever mechanism assembly, 11 is a float assembly, 12 is a liquid level gauge assembly, 21 is a steam pipeline steam trap exhaust device, 22 is a steam-water separator, 23 is a compressed air storage device, 24 is a drainage system, 25 is a pneumatic steam trap pump, 26 is a filter, and 27 is a condenser. DETAILED DESCRIPTION
[0015] The present invention is further described in detail below with reference to the accompanying drawings and specific embodiments.
[0016] like Figure 1 As shown, a nuclear power steam-driven auxiliary water feed pump includes a pump body 1, a pump cover 2, a gasket 3, an exhaust valve assembly 4, an intake valve assembly 5, an inlet check valve 6, an outlet check valve 7, a linkage mechanism assembly 8, a steam trap assembly 9, a lever mechanism assembly 10, a float assembly 11 and a liquid level meter assembly 12.
[0017] Specifically, a liquid level gauge assembly 12 is installed on one side of the outside of the pump body 1, one end of the liquid level gauge assembly 12 is located at the lower part of the pump body 1, and the other end is located at the upper part of the liquid level gauge assembly 12, one side of the pump body 1 is connected to the pump cover 2, the pump body 1 and the pump cover 2 are provided with a gasket 3, the upper part of the pump cover 2 is respectively provided with an exhaust valve assembly 4 and an intake valve assembly 5, the exhaust valve assembly 4 is connected to the linkage mechanism assembly 8, the linkage mechanism assembly 8 is connected to the lever mechanism assembly 10, the lever mechanism assembly 10 is connected to the float assembly 11, the lower water outlet check valve 7 on the outside of the pump cover 2, and the lower part of the pump cover 2 is also provided with a drain valve assembly 9, which performs draining and closing through the action of the connecting rod mechanism assembly 10, and discharges the drain to the downstream water outlet check valve 7 and the downstream drainage pipe, and the middle of the pump cover 2 is connected with an inlet check valve 6.
[0018] like Figure 2 As shown, a nuclear power steam-driven auxiliary feedwater pump and related system drain recovery device includes a steam pipeline drain and exhaust device 21, a steam-water separator 22, a compressed air storage device 23, a drainage system 24, a pneumatic drain pump 25, a filter 26 and a condenser 27. The steam pipeline drain and exhaust device 21 is connected to the steam-water separator 22, the steam-water separator 22 is respectively connected to the drainage system 24 and the pneumatic drain pump 25, the pneumatic drain pump 25 is connected to the compressed air storage device 23, the pneumatic drain pump 25 is connected to the filter 26, the filter 26 is connected to the condenser 27, the steam-water separator 22 is also connected to the exhaust port, and the pneumatic drain pump 25 is connected to the exhaust port.
[0019] The drain of the pneumatic auxiliary feedwater pump (position elevation of about 0m) and the drain and exhaust of the front and rear steam pipelines are collected in the steam-water separator (position elevation of about -3.4m), and the separated drain flows into the pneumatic drain pump (elevation of about -7.0m), and drains to the condenser after filtration. An overflow pipeline is set in front of the pneumatic drain pump, and the highest point is more than 1m higher than the bottom of the steam-water separator. A water seal is set downstream of the filter, and the highest point elevation must be greater than 5m. The core equipment is the pneumatic drain pump.
[0020] The structure of the pneumatic drain pump is a float-type drain pump driven by compressed air (or other gases such as steam according to user needs). The inlet and outlet check valves are designed. The lifting of the float can interlock and trigger the opening and closing of the drainage, air intake and exhaust valves to achieve the function of intermittent draining.
[0021] 1) Under normal working conditions, the exhaust valve of the drain pump is open, the pump cavity is at normal pressure, the drain enters the pump cavity due to gravity, the float rises with the increase of liquid level, and under the action of the linkage assembly in the pump, the power gas source inlet valve is opened, the exhaust valve is closed, the air intake pressure in the cavity increases, and the water inflow stops. After the pressure increases, the drainage check valve opens, the pressure of the power medium forces the condensed water to be discharged quickly, the float drops, the linkage assembly resets, the power medium inlet valve (inlet valve) is closed, the exhaust valve is opened, the drainage valve is closed, the pump cavity returns to normal pressure, and the water inflow resumes. This reciprocating cycle has achieved the function of intermittent draining.
[0022] 2) In the event of a fault, when the drain pump stops taking in or discharging water, the upstream drain will overflow into the pit of the drainage system through the upstream overflow pipeline, which will not cause the upstream pneumatic auxiliary water supply pump to become unavailable due to poor drainage.
[0023] 1. The steam pipeline and main equipment of the drain exhaust source are at an elevation of about 0m, the steam-water separator is at an elevation of about -3.4m, and the pneumatic drain pump is at an elevation of about -7.0m. The heights decrease in sequence, but the specific values are not limited.
[0024] 2. The highest point of the overflow pipeline is more than 1m above the bottom of the steam-water separator.
[0025] 3. The elevation of the highest point of the downstream water seal must be greater than 5m. The value is not limited. The principle is to ensure that the water seal can provide a maximum pressure difference of 1 atmosphere.
Claims
1. A drainage recovery device including a nuclear power steam-driven auxiliary feedwater pump, characterized in that: It includes a steam pipeline drain and exhaust device, a steam-water separator, a compressed air storage device, a drainage system, a nuclear power steam-driven auxiliary feed water pump, a filter and a condenser. The steam pipeline drain and exhaust device is connected to the steam-water separator, the steam-water separator is respectively connected to the drainage system and the nuclear power steam-driven auxiliary feed water pump, the nuclear power steam-driven auxiliary feed water pump is connected to the compressed air storage device, the nuclear power steam-driven auxiliary feed water pump is connected to the filter, and the filter is connected to the condenser; The steam-water separator is connected to the exhaust port; The nuclear power steam-driven auxiliary feedwater pump is connected to the exhaust port. The nuclear power steam-driven auxiliary water supply pump comprises a pump body, a pump cover, a gasket, an exhaust valve assembly, an air inlet valve assembly, a water inlet check valve, a water outlet check valve, a linkage mechanism assembly, a steam trap assembly, a lever mechanism assembly, a float assembly and a liquid level gauge assembly. A liquid level gauge assembly is installed on one side of the pump body, one side of the pump body is connected to the pump cover, an exhaust valve assembly and an air inlet valve assembly are respectively arranged on the upper part of the pump cover, the exhaust valve assembly is connected to the linkage mechanism assembly, the linkage mechanism assembly is connected to the lever mechanism assembly, the lever mechanism assembly is connected to the float assembly, a water outlet check valve is arranged at the lower part of the outer side of the pump cover, a steam trap assembly is also arranged at the lower part of the pump cover, and an inlet check valve is connected to the middle of the pump cover; One end of the liquid level gauge assembly is located at the lower part of the pump body; One end of the liquid level gauge assembly is located at the upper part of the pump body; A gasket is arranged between the pump body and the pump cover.
Citation Information
Patent Citations
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