CN212833221U

CN212833221U - Nuclear power plant steam generator sewage purification system

Info

Publication number: CN212833221U
Application number: CN202021393810.5U
Authority: CN
Inventors: 牛婷婷; 江浩; 曹卫荣; 陈煜�; 武心壮; 夏栓; 刘春丽; 陈旭; 詹敏明
Original assignee: Shanghai Nuclear Engineering Research and Design Institute Co Ltd
Current assignee: Shanghai Nuclear Engineering Research and Design Institute Co Ltd
Priority date: 2020-07-15
Filing date: 2020-07-15
Publication date: 2021-03-30
Anticipated expiration: 2030-07-15

Abstract

The utility model discloses a clean system of nuclear power plant's steam generator sewage, steam generator sewage exit linkage ionization desalination device, the steam generator sewage warp the clean fluid and the concentrated fluid that flow out behind the ionization desalination device flow through respectively radiation instrument (R01, R02) and radiate the detection, warp radiation instrument (R01, R02) detect qualified water and connect factory building drainage system or condensate system, warp radiation instrument (R01, R02) detect nonconforming water and connect radioactive waste liquid treatment system. The utility model adopts the method for purifying the sewage of the steam generator, which can efficiently remove the impurity ions in the sewage, uses the ionization desalination device with long service life and high temperature resistance, does not need regeneration and chemical cleaning, and has small volume and small secondary waste generation compared with the ion exchange resin process; the ionization desalination device can flexibly control the number of the EDI modules according to the flow of the sewage flow so as to adapt to the change of the flow of the sewage flow under the working condition.

Description

Nuclear power plant steam generator sewage purification system

Technical Field

The utility model belongs to the technical field of the blowdown of nuclear power plant, especially, relate to the purification technology of steam generator blowdown water.

Background

Blowdown from steam generators of pressurized water reactor nuclear power plants is critical to reduce sludge deposition in the steam generators, maintain integrity of heat transfer tubes of the steam generators, and control water chemistry on the secondary side of the steam generators. The main impurities in the sewage of the steam generator are Na-, Cl-, SO 42-and the like, the sewage is purified by adopting an ion exchange process in the traditional pressurized water reactor nuclear power plant, and in order to ensure the purification effect, acid-base regenerated resin or resin replacement is required regularly, and a large amount of secondary waste is generated during the replacement.

The utility model provides a continuous ionization desalination (EDI) processing technology for purifying steam generator blow off water compares in traditional ion exchange processing technology, but has continuous regeneration, long service life, fortune dimension simple and convenient, take up an area of for a short time, secondary waste produces volume little etc. and is showing the advantage.

SUMMERY OF THE UTILITY MODEL

In order to guarantee pressurized water reactor nuclear power plant steam generator blowdown ability, the utility model provides a clean system of nuclear power plant steam generator blow off water, a serial communication port, steam generator blow off water exit linkage ionization desalination device, steam generator blow off water warp the clean fluid and the concentrated fluid that flow out behind the ionization desalination device flow through respectively radiation instrument (R01, R02) and radiate the detection, warp radiation instrument (R01, R02) detect qualified water and connect factory building drainage system or condensate system, warp radiation instrument (R01, R02) detect unqualified water and connect radioactive waste liquid treatment system.

Preferably, the ionization desalination device is a filter and an ionization desalination module.

Preferably, the filter is a two-stage filter (MT01, MT02) that removes suspended solids and particulate matter.

Preferably, the filter is provided with a differential pressure meter (PD01) at the upstream and downstream.

Preferably, the ionization and desalination module is respectively provided with conductivity meters (C01, C02 and C03) before the inlet and after the outlets of the cleaning fluid and the concentrated fluid, and the operation condition of the ionization and desalination module is monitored.

Preferably, a flow control pressure reducing valve (V003) is provided in front of the inlet of the ionization and desalination device to adjust the inlet pressure.

Preferably, the steam generator sewage outlet is provided with a regeneration heat exchanger, and the regeneration heat exchanger returns the heat of the steam generator sewage to the condensed water.

Preferably, the regenerative heat exchanger is a shell and tube counter-flow heat exchanger, the steam generator blowdown water flows through the tube side, and the condensate water flows through the shell side.

Preferably, the radiation meters (R01, R02) are respectively connected with three-way valves (V007, V010) to switch and control the flow direction of the fluid.

Preferably, pressure regulating valves (V006, V009) are respectively provided in front of the radiation meters (R01, R02) for maintaining a constant pressure of the cleaning fluid and the concentrating fluid.

Preferably, a pressure relief valve (V018) is arranged in front of the inlet of the radioactive waste liquid treatment system and used for adjusting overpressure of the low-pressure part of the radioactive waste liquid treatment system.

The utility model adopts the method for purifying the sewage of the steam generator, which can efficiently remove the impurity ions in the sewage, uses the ionization desalination device with long service life and high temperature resistance, does not need regeneration and chemical cleaning, and has small volume and small secondary waste generation compared with the ion exchange resin process; the ionization desalination device can flexibly control the number of the EDI modules according to the flow of the sewage flow so as to adapt to the change of the flow of the sewage flow under the working condition.

Drawings

FIG. 1 is a schematic view of a steam generator blowdown stream purge flow scheme.

FIG. 2 is a schematic flow chart of an ionization desalination device.

Detailed Description

In order to make the above objects, features and advantages of the present invention more comprehensible, the present invention is described in detail with reference to the accompanying drawings and the detailed description.

The utility model provides a clean system of nuclear power plant steam generator blow off water, impurity ion purifier is one set of ionization desalination device (including filter and ionization desalination module), and other supporting devices include a regenerative heat exchanger, relevant isolating valve and control valve, measurement and control instrument etc.. The utility model provides a steam generator blowdown flows and purifies flow path is shown in figure 1. The blow-down stream is cooled by a regenerative heat exchanger, and heat is transferred to the condensed water from the upstream of the shaft seal steam condenser in the heat exchanger. After cooling, the sewage flows through a flow control pressure reducing valve V003, and flows into an ionization desalting device after pressure reduction to remove impurities in the sewage. The EDI clean flow purified by the ionization desalination device returns to a condensate system for reuse or is discharged into a plant for drainage after being measured by the radiation instrument R01, and the EDI concentrated flow is discharged into the plant for drainage after being measured by the radiation instrument R02. If the radiation meter is unqualified in measurement, the EDI clean flow, the concentration flow and the inlet water are discharged to a radioactive waste liquid treatment system for treatment, and the three-way valves V007 and V010 are switched to control the flow direction of the fluid. The sewage discharge flow can be controlled by automatically or manually adjusting the valve position of V003. The pressure control valve V015 is arranged at a position close to a condenser nozzle, and cavitation and flash evaporation of a pipeline in front of the valve due to condenser vacuum are prevented. The pressure regulating valve V009 is used to maintain a constant pressure in the EDI concentrate flow path, ensure a pressure differential across the EDI module, and balance the flow of the cleaning stream and the concentrate stream. A pressure relief valve V018 is used to prevent over-pressurization of the low pressure portion of the system. The utility model provides a regenerative heat exchanger is shell-and-tube type countercurrent heat exchanger, and the blowdown stream flows through pipe side (high pressure), and the condensate flow is through shell side (low pressure).

The flow chart of the ionization desalination device provided by the utility model is shown in figure 2. The sewage flow of the steam generator enters two-stage filters MT01 and MT02 after being cooled and depressurized, suspended solids and particulate matters are removed, and the filter precision is 5 microns and 0.1 micron respectively. After filtration, the sewage flows into an EDI module (MV 01-MV 0X) to remove ionizable impurity ions such as Na +, Cl-, SO 42-and the like. And controlling the configuration quantity and the operation quantity of EDI in the system according to the flow of the sewage flow under different operation conditions and the processing flow limit value of a single EDI module. A pressure difference meter PD01 is arranged upstream and downstream of the filter, conductivity meters (C01, C02 and C03) are arranged at the inlet, the clean flow and the concentrated flow outlet of the EDI module, and the operation condition of the whole ionization and desalination device is monitored.

The utility model discloses use specific EDI module can be no less than 60 ℃ operating temperature for a long time under operation, the module life-span is no less than 3 years, to impurity ions such as Na +, Cl-, SO 42-the clearance be greater than or equal to 95%, purify the rate of recovery that flows and be greater than or equal to 90%. Ammonia water, and pH regulator commonly used in two loops such as oxocyclohexylamine (morpholine), Methyl Propoxide (MPA) or Ethanolamine (ETA) have no influence on the operation and performance of the ionization desalting device. The service life of the EDI module is 3-5 years, and no chemical cleaning or maintenance is needed during the operation. The volume of the whole ionization desalination device is about 1/6 of the ion exchange resin bed.

It will be apparent to those skilled in the art that various changes and modifications may be made without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims and their equivalents, the present invention is also intended to encompass such modifications and variations. The above-described embodiments or implementations are merely illustrative of the present invention, which may be embodied in other specific forms or arrangements without departing from the spirit or essential characteristics thereof. The described embodiments are, therefore, to be considered in all respects as illustrative and not restrictive. The scope of the invention should be determined by the appended claims, and any changes that are equivalent to the intent and scope of the claims are intended to be embraced therein.

Claims

1. The utility model provides a clean system of nuclear power plant steam generator sewage, a serial communication port, steam generator sewage exit linkage ionization desalination device, steam generator sewage warp the clean fluid and the concentrated fluid of outflow behind the ionization desalination device are flowed through respectively and are radiated the detection by radiation instrument (R01, R02), warp radiation instrument (R01, R02) detect qualified water and connect factory building drainage system or condensate system, warp radiation instrument (R01, R02) detect unqualified water and connect radioactive waste liquid treatment system.

2. The system for purifying nuclear power plant steam generator blow down water of claim 1 wherein said ionization desalination device is a filter and an ionization desalination module.

3. The system for purifying nuclear power plant steam generator blow down water of claim 2 wherein the filter is a two stage filter (MT01, MT02) that removes suspended solids and particulate matter.

4. The system for purifying nuclear power plant steam generator blow down water of claim 2 wherein a pressure differential gauge (PD01) is provided upstream and downstream of the filter.

5. The system for purifying nuclear power plant steam generator waste water of claim 2 wherein said ionization and desalination module is provided with conductivity meters (C01, C02, C03) before the inlet and after the outlet of said cleaning fluid and said concentrating fluid, respectively, and the operation of said ionization and desalination module is monitored.

6. The system for purifying sewage from a steam generator of a nuclear power plant as claimed in claim 1, wherein a flow control pressure reducing valve (V003) is provided in front of the inlet of the ionization and desalination device to adjust the inlet pressure.

7. The system for purifying nuclear power plant steam generator waste water of claim 1 wherein the steam generator waste water outlet is provided with a regenerative heat exchanger that returns heat from the steam generator waste water to the condensate water.

8. The system for purifying nuclear power plant steam generator waste water of claim 7 wherein the regenerative heat exchanger is a shell and tube counter-flow heat exchanger, the steam generator waste water flows through the tube side and the condensate flows through the shell side.

9. The system for purifying sewage from a steam generator of a nuclear power plant as claimed in claim 1, wherein the radiation meters (R01, R02) are respectively connected with three-way valves (V007, V010) for switching and controlling the flow direction of the fluid.

10. The system for purifying sewage from a steam generator of a nuclear power plant as claimed in claim 1, wherein pressure regulating valves (V006, V009) are provided in front of the radiation meters (R01, R02), respectively, for maintaining a constant pressure of the cleaning fluid and the concentrating fluid.

11. The system for purifying sewage from a steam generator of a nuclear power plant as claimed in claim 1, wherein a pressure relief valve (V018) is provided in front of the inlet of the radioactive liquid waste treatment system for adjusting the overpressure in the low pressure part of the radioactive liquid waste treatment system.