CN209325422U - A kind of over pressure protective device - Google Patents
A kind of over pressure protective device Download PDFInfo
- Publication number
- CN209325422U CN209325422U CN201821984236.3U CN201821984236U CN209325422U CN 209325422 U CN209325422 U CN 209325422U CN 201821984236 U CN201821984236 U CN 201821984236U CN 209325422 U CN209325422 U CN 209325422U
- Authority
- CN
- China
- Prior art keywords
- power plant
- nuclear power
- control
- protective device
- pressure
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
Landscapes
- Testing Or Calibration Of Command Recording Devices (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The utility model belongs to nuclear power plant's primary Ioops monitoring technical field; more particularly to a kind of over pressure protective device; it is arranged on the pipeline of the primary Ioops of nuclear power plant; sensor device on the spot including the hydraulic pressure, temperature that are arranged on the primary Ioops, can measure the primary Ioops passes through the control enclosure means of the control cable control sensor device on the spot.Primary Ioops pressure and its rate of change, the temperature of pressure vessel and its rate of change can be monitored using over pressure protective device described in the utility model in real time; and corresponding alarm can be generated; can reach ensures nuclear power plant in the case where being more than design basis pressure; pressure is always within control range, it is ensured that the safety of equipment is unaffected.
Description
Technical field
The utility model belongs to nuclear power plant's primary Ioops monitoring technical field, and in particular to a kind of over pressure protective device.
Background technique
According to associated safety regulation, nuclear power plant needs to be implemented hydrostatic test in process of construction.Especially nuclear power plant one is returned
Pipeline equipment is the second safety curtain of nuclear power plant and safety, it is necessary to assure its safety.Two generation presurized water reactor primary Ioops design base
Quasi- pressure is 17.2MPa, needs to reach 1.33 times of reference pressure according to laws and regulations requirement hydrostatic test, both 22.8MPa.Exceeding
When design basis pressure, nuclear power plant does not have pressure transmitter to monitor primary Ioops pressure, and primary Ioops pressure is in this case
Uncontrollable state has great risk, it is possible to fatal harm is caused to nuclear power plant's capital equipment.Existing settling mode is
Before Primary hydraulic test, by increasing interim control measure, interim instrument and pipeline is installed to implement, are related to instrument
The a series of activities such as installation, cable laying, system debug, program composition, expend a large amount of manpower and material resources, and benefit cannot be repeated
With causing capacity utilization low.
Utility model content
In view of the deficiencies in the prior art, the purpose of the utility model is to provide one kind in nuclear power plant's primary Ioops hydraulic pressure
Monitoring primary Ioops pressure during test and preventing primary Ioops pressure is more than the protective device of desired value.This device is using high-precision
Spend sensor measurement physical quantity on the spot;Logic control is realized using the control cabinet of high integration, can ensure that primary Ioops hydraulic pressure tries
Primary Ioops pressure is within controlled range during testing.
To achieve the above objectives, the technical solution adopted in the utility model is: a kind of over pressure protective device, is arranged in core
On the pipeline of the primary Ioops of power plant, wherein including be arranged on the primary Ioops, the primary Ioops can be measured hydraulic pressure, temperature
The sensor device on the spot of degree passes through the control enclosure means of the control cable control sensor device on the spot.
Further, the control enclosure means are also connected to nuclear power plant's control system of the nuclear power plant.
Further, the sensor device on the spot includes precision pressure gauge and accurate platinum resistance thermometer.
Further, the control enclosure means include be arranged in it is inside small-sized cabinet, by analog input fastener with
The primary processor that the precision pressure gauge is connected with the accurate platinum resistance thermometer, the primary processor pass through interchanger and institute
It states nuclear power plant's control system to be connected, further includes output switch parameter fastener, power module.
Further, the control enclosure means and nuclear power plant's control system of the nuclear power plant are connected by hardwire or network
It connects, guarantee has redundant communication paths between the two.
It further, also include a PC in the control enclosure means, the PC is built-in described to be sensed on the spot for controlling
The page of the control software of device device and the display data content of sensor device on the spot, can display real-time the main process task
Numerical value in device, and the logic in the primary processor can be edited.
Further, the precision pressure gauge is 2 pieces, and the precision platinum resistance temperature is calculated as 6.
The beneficial effects of the utility model are as follows:
In the case where nuclear power plant's primary Ioops hydrostatic test pressure is more than design basis, the utility model can monitor in real time
Primary Ioops pressure and its rate of change, the temperature of pressure vessel and its rate of change, and corresponding alarm can be generated, it can reach
Ensure the primary Ioops of nuclear power plant in the case where being more than design basis pressure, pressure is always within control range, it is ensured that equipment
Safety it is unaffected.Disperse relative to equipment used by the existing hydrostatic test for primary Ioops, temporarily install, is interim
The mode of adjustment, device provided by the utility model are complete equipment, replace machinery instrument using intelligence instrument, improve measurement
Precision reduces signal in the transmitting of different rack rooms, increases signal accuracy, reusable in different nuclear power projects, greatly drops
Low cost shortens the time of Primary hydraulic test.
Detailed description of the invention
Fig. 1 is the schematic diagram of over pressure protective device described in specific embodiment of the present invention;
In figure: 1- primary processor, 2- analog input fastener, 3- interchanger, 4- precision pressure gauge, 5- precision platinum resistance temperature
Degree meter, 6-PC, 7- nuclear power plant control system, 8- trolley.
Specific embodiment
The utility model is further described with reference to the accompanying drawings and examples.
As shown in Figure 1, a kind of over pressure protective device, is arranged on the pipeline of the primary Ioops of nuclear power plant, including pass on the spot
Sensor arrangement, control enclosure means two large divisions, control enclosure means, which pass through control cable connection and control sensor on the spot, to be filled
It sets.Control enclosure means are also connected to nuclear power plant's control system 7 of nuclear power plant.
Wherein, sensor device is arranged on the primary Ioops of nuclear power plant on the spot, for measuring hydraulic pressure, the temperature of primary Ioops.
Sensor device includes precision pressure gauge 4 and accurate platinum resistance thermometer 5 on the spot.Wherein, precision pressure gauge 4 is 2
Block, accurate platinum resistance thermometer 5 are 6.
Controlling enclosure means includes primary processor 1, analog input fastener 2, interchanger 3, output switch parameter fastener, power supply
Module, AO DO AI (including platinum resistance) module, fan, bottom plate, guide rail and cable.A minicomputer is all disposed with upper-part
In rack in cabinet, small-sized cabinet is arranged on trolley 8, convenient for being moved as needed.Primary processor 1 is defeated by analog quantity
Enter fastener 2 to be connected with precision pressure gauge 4 and accurate platinum resistance thermometer 5, primary processor 1 is controlled by interchanger 3 and nuclear power plant
System 7 is connected.Controlling also includes a PC6 (namely engineer station) in enclosure means, and PC6 is built-in to be sensed on the spot for controlling
The control software of device device and the page for showing the data content of sensor device on the spot, can display real-time in primary processor 1
Numerical value, and the logic in primary processor 1 can be edited.
Analog signals (pressure and temperature) pass through control cable transmission to analog input fastener 2, analog signal input card
After part 2 is handled signal;Be sent to primary processor 1, primary processor 1 realizes logic function, and logical consequence be sent to PC6 and
Nuclear power plant's control system 7 is shown.PC6 can show the signal of all analog quantitys, while can modify primary processor 1 by PC6
In configuration and parameter.
Control enclosure means and nuclear power plant's control system 7 of nuclear power plant (such as pass through light by hardwire or network connection
It is fine), guarantee has redundant communication paths between the two.
Numerical value comprising precision pressure gauge 4 and accurate platinum resistance thermometer 5 in control software shows, can show boosting speed
Rate, overpressure protection logic, relative alarm signal, and all by page centralized displaying, and above- mentioned information can be sent to nuclear power plant
In control system 7.
Control software is able to achieve importing/export to the sensing data of sensor device on the spot, the people of graphical/tabular
Machine interface display can edit, search, screen sensing data.Ethernet based on TCP/IP communications protocol is able to achieve and nuclear power plant
The communication of control system 7.
Controlling software can also be when pressure be more than permissible range, and corresponding valve in primary Ioops is opened in control, reaches drop
The purpose of the pressure of low primary Ioops.
Device described in the utility model is not limited to embodiment described in specific embodiment, those skilled in the art
Technical solution according to the present utility model obtains other embodiments, also belongs to the technological innovation scope of the utility model.
Claims (7)
1. a kind of over pressure protective device, is arranged on the pipeline of the primary Ioops of nuclear power plant, it is characterized in that: including being arranged described
On primary Ioops, the sensor device on the spot of hydraulic pressure that the primary Ioops can be measured, temperature, it is described just by control cable control
The control enclosure means of ground sensor device.
2. a kind of over pressure protective device as described in claim 1, it is characterized in that: the control enclosure means also with the core
Nuclear power plant's control system (7) of power plant is connected to.
3. a kind of over pressure protective device as claimed in claim 2, it is characterized in that: the sensor device on the spot includes precision
Pressure gauge (4) and accurate platinum resistance thermometer (5).
4. a kind of over pressure protective device as claimed in claim 3, it is characterized in that: the control enclosure means include that setting exists
It is inside small-sized cabinet, pass through analog input fastener (2) and the precision pressure gauge (4) and the precision platinum resistance thermometer
(5) connected primary processor (1), the primary processor (1) are connected by interchanger (3) with nuclear power plant's control system (7),
It further include output switch parameter fastener, power module.
5. a kind of over pressure protective device as claimed in claim 4, it is characterized in that: the control enclosure means and the nuclear power
Nuclear power plant's control system (7) of factory has redundant communication paths by hardwire or network connection, guarantee between the two.
6. a kind of over pressure protective device as claimed in claim 4, it is characterized in that: also including one in the control enclosure means
Platform PC (6), the PC (6) are built-in for controlling the control software of sensor device on the spot and the display sensor on the spot
The page of the data content of device can display real-time the numerical value in the primary processor (1), and can be to the primary processor
(1) logic in is edited.
7. a kind of over pressure protective device as claimed in claim 3, it is characterized in that: the precision pressure gauge (4) is 2 pieces, institute
Stating accurate platinum resistance thermometer (5) is 6.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201821984236.3U CN209325422U (en) | 2018-11-29 | 2018-11-29 | A kind of over pressure protective device |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201821984236.3U CN209325422U (en) | 2018-11-29 | 2018-11-29 | A kind of over pressure protective device |
Publications (1)
Publication Number | Publication Date |
---|---|
CN209325422U true CN209325422U (en) | 2019-08-30 |
Family
ID=67712096
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN201821984236.3U Active CN209325422U (en) | 2018-11-29 | 2018-11-29 | A kind of over pressure protective device |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN209325422U (en) |
-
2018
- 2018-11-29 CN CN201821984236.3U patent/CN209325422U/en active Active
Similar Documents
Publication | Publication Date | Title |
---|---|---|
CN107065743B (en) | Irrigation area informatization system and management method thereof | |
CN101255947B (en) | Metered system for automatically capturing fluid flux | |
CN203772488U (en) | LNG storage tank leakage and cooling temperature monitoring system based on distributed fiber temperature measurement method | |
CN202837989U (en) | Dam safety automatic monitoring system | |
CN104458316A (en) | Overall physical model test platform for transient process of hydropower station | |
CN108427093A (en) | A kind of calibrating and measuring system and method for watt-hour meter automatic verification device | |
KR102021431B1 (en) | Instrument control equipment Remote monitoring and control system | |
CN109583783A (en) | A kind of configuration design method of plate nut production line | |
CN104881728A (en) | Food safety production traceability monitoring system service platform | |
CN103676661B (en) | Multifunction emulation verifies system and its emulation verification method | |
CN105182773A (en) | Data detection system and method for run-up test of aeroengine | |
CN204302026U (en) | Transient Process of Hydropower Station integrated physical model test platform | |
CN111897270A (en) | Real-time online health state monitoring system for ship lock miter gate and hoist | |
CN105551553A (en) | Pilot type safety valve jumping monitoring device and method of PWR (Pressured Water Reactor) nuclear power station | |
CN110530409A (en) | A kind of on-line automatic measurement and calibration instrument, calibration method and computer media | |
CN209325422U (en) | A kind of over pressure protective device | |
CN208903300U (en) | A kind of construction risk automatic monitoring system based on BIM technology | |
CN110132449A (en) | A kind of temperature monitoring method at equipment position | |
Kwon et al. | Technical review on the localized digital instrumentation and control systems | |
CN203850922U (en) | Secondary device system with advantages of stable operation and convenient monitoring | |
CN1987369B (en) | Multifunctional sensor testing device | |
CN201347773Y (en) | Drilling mud storage tank liquid level alarm system based on PLC control | |
CN104409119B (en) | A kind of nuclear power station flow sampling display system and method | |
Epifancev et al. | Problems and advantages of SCADA systems when performing measurements at hazardous production technologies | |
CN111580504A (en) | Simulation test platform of submarine cable oil pump station control system |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
GR01 | Patent grant | ||
GR01 | Patent grant |