CN203858871U - Control device of nuclear power plant air emission system - Google Patents
Control device of nuclear power plant air emission system Download PDFInfo
- Publication number
- CN203858871U CN203858871U CN201420124055.9U CN201420124055U CN203858871U CN 203858871 U CN203858871 U CN 203858871U CN 201420124055 U CN201420124055 U CN 201420124055U CN 203858871 U CN203858871 U CN 203858871U
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- control device
- power plant
- nuclear power
- pressure
- temperature
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- 238000001816 cooling Methods 0.000 abstract description 14
- 230000001276 controlling effect Effects 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 230000002411 adverse Effects 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000000605 extraction Methods 0.000 description 1
- 230000000116 mitigating effect Effects 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
- 230000007704 transition Effects 0.000 description 1
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The utility model relates to a control device of a nuclear power plant air emission system. The control device comprises an air emission valve control element which is connected with an air emission valve on an air emission pipe and can control the opening of the air emission valve. The air emission valve control element comprises a three-channel threshold switching switch, a proportional integral controller, a setting value opening double-channel switching switch and an electrical converter which are connected in order. By using the technical scheme of the utility model, the realization of the diversification of cooling and heat exhaust control modes is ensured in the period of power plant shutdown, in the condition of an accident, the rely on operator intervention is small, the cooling rate of a loop is accurately controlled, the reliability of the system is high, and the ability to alleviate the accident is strong.
Description
Technical field
The utility model belongs to nuclear power field, is specifically related to the control device of a kind of nuclear power plant airborne release system.
Background technology
Nuclear power plant's airborne release system is to reduce the important system of temperature, pressure in nuclear steam supply system, when load dump and condenser are when unavailable, and the operating point that need to be cooled to residual heat removal system to drop into reactor coolant loop by this system.In the design of commercial nuclear power system in the past, during power plant's shutdown, airborne release system need to be with the cooldown rate of 28 ℃/h a cooling loop, operator need to be according to the temperature variations in a loop, and manual adjustments airborne release valve opening or atmospheric dump valve setting valve meet the requirement of cooldown rate; Under the accident of steam generator tube rupture, also need the atmospheric dump valve of the intact steam generator of operator's manual adjustments to strengthen cooling to a loop.These operations all depend on operator's judgement, and the reliability of completion system function and accident mitigation are brought to adverse influence.
Utility model content
For the defect existing in prior art, the utility model provides the control device of a kind of nuclear power plant airborne release system, adopts this control device, can flexibly and accurately control the cooldown rate of cooling circuit; The reliability of system is higher, and the ability of alleviation accident is stronger.
For reaching above object, the technical solution adopted in the utility model is: the control device that a kind of nuclear power plant airborne release system is provided, this control device comprises atmospheric dump valve control element, described atmospheric dump valve control element is connected with the atmospheric dump valve on airborne release pipeline, and described atmospheric dump valve control element comprises the triple channel threshold value change-over switch that is connected successively, pi controller, setting valve aperture binary channels change-over switch and electropneumatic transducer.
Further, described triple channel threshold value change-over switch is connected with three passages, can realize three-aisled switching, and described three passages are respectively first passage, fixedly setting valve station and unsteady setting valve station; Described triple channel threshold value change-over switch is also connected with a circuit pressure temperature transmitter.
Further, described first passage comprises temperature indicator (TI), pressure indicator and signal processing card part, and described temperature indicator (TI) is connected with described signal processing card part respectively with pressure indicator; Described pressure indicator is also connected with described pi controller.
Further, described pressure indicator comprises the high card selection part of pressure and three pressure transducers that are arranged in parallel that are connected with the high card selection part of described pressure.
Further, described temperature indicator (TI) comprises the high card selection part of temperature and three temperature sensors that are arranged in parallel that are connected with the high card selection part of described temperature.
Further, described electropneumatic transducer is connected with source of the gas by gas supply line.
Useful technique effect of the present utility model is:
(1) during power plant's shutdown, can realize the variation of cooling heat extraction control mode, make control mode more flexible, rate of temperature fall is more accurate;
(2) under accident conditions, can when surpassing change-over switch threshold value, sensor signal automatically switch to fast in the type of cooling, and the cooldown rate that reaches 100 ℃/h is a cooling loop automatically, guarantees reactor safety;
(3) this system less relies on operator intervention under accident conditions, and the reliability of system is higher, and the ability of alleviation accident is stronger.
Accompanying drawing explanation
The structural representation of the control device of Tu1Shi the utility model nuclear power plant airborne release system;
Fig. 2 a is the structural representation of pressure indicator in Fig. 1;
Fig. 2 b is the structural representation of temperature indicator (TI) in Fig. 1.
Embodiment
Below in conjunction with accompanying drawing, embodiment of the present utility model is described in further detail.
The structural representation of the control device of Tu1Shi the utility model nuclear power plant airborne release system; As shown in Figure 1, nuclear power plant's airborne release system comprises airborne release pipeline N1 to N2 and is arranged on the atmospheric dump valve 13 on airborne release pipeline, in order to meet the requirement of cooling circuit cooldown rate, on atmospheric dump valve 13, be provided with the control device of airborne release system, this control device can be controlled the aperture of atmospheric dump valve 13.
The control device of nuclear power plant's airborne release system comprises atmospheric dump valve control element 1, and this atmospheric dump valve control element 1 comprises triple channel threshold value change-over switch 5, pi controller 8, setting valve aperture binary channels change-over switch 9 and electropneumatic transducer 12 successively; Wherein, in setting valve aperture binary channels change-over switch 9, be connected with the opening adjuster 10 of adjustable double channel change-over switch 9.
Triple channel threshold value change-over switch 5 is connected with three passages, can realize three-aisled switching, and described three passages are respectively fast cooling first passage 2, fixedly setting valve station 3 and unsteady setting valve station 4; Described triple channel threshold value change-over switch 5 is also connected with a circuit pressure temperature transmitter 6, and the temperature transition that the pressure that this pressure and temp transmitter 6 can be surveyed pressure measuring element and temperature-measuring element are surveyed becomes the electric signal of 4-20mA.
First passage 2 comprises temperature indicator (TI) 14, pressure indicator 7 and signal processing card part 15; Temperature indicator (TI) 14 is connected with signal processing card part 15 respectively with pressure indicator 7; Pressure indicator 7 is also connected with pi controller 8.
Atmospheric dump valve 13 is pneumatic control valve, by source of the gas 11 air feed, gas supply line by three series connection between pneumatic control valve and source of the gas 11 is connected, and three gas supply lines are respectively the first gas supply line N3 to N4, the second gas supply line N4 to N5, the 3rd gas supply line N5 to N6.In addition, electropneumatic transducer 12 is also by source of the gas 11 air feed, and electropneumatic transducer 12 is connected with source of the gas 11 by the first gas supply line N3 to N4.
As shown in Figure 2 a, pressure indicator 7 comprises the high card selection part 19 of pressure and three pressure transducers that are arranged in parallel 16,17,18 that are connected with the high card selection part 19 of pressure, three pressure transducers 16,17,18 are all arranged on main steam pressure hydraulic piping, measure the pressure of main steam pressure hydraulic piping.Top pressure in the high card selection part 19 selection pressure sensors 16,17,18 of pressure.
As shown in Figure 2 b, temperature indicator (TI) 14 comprises the high card selection part 23 of temperature and three temperature sensors that are set up in parallel 20,21,22 that are connected with the high card selection part 23 of temperature; Three temperature sensors 20,21,22 are all arranged on the pipeline of core exit, measure the temperature of core exit.The high card selection part 23 of temperature is selected top pressure in temperature sensor 20,21,22.
In sum, first passage 2 flows to pi controller 8 by triple channel threshold value change-over switch 5 by signal value after the core exit temperature high-value signal of the main steam pressure high-value signal of pressure indicator 7 output and temperature indicator (TI) 14 outputs is transferred to and is processed in signal processing card part 15; Now, the main steam pressure high-value signal of pressure indicator 7 outputs directly flows to pi controller 8 without adjusting; Pi controller 8 is by after adjusting being transported to result setting valve aperture binary channels change-over switch 9, setting valve aperture binary channels change-over switch 9 is selected after suitable aperture by opening adjuster 10, through electropneumatic transducer 12, change, finally reach the aperture object of controlling atmospheric dump valve 13.
During power plant's shutdown, the switching that operator can operate triple channel threshold value change-over switch 5 regulates the temperature in a loop.As triple channel threshold value change-over switch 5 is switched to first passage 2, can realize cooling fast; As triple channel threshold value change-over switch 5 is switched to fixedly setting valve station 3, can carry out cooling according to the pressure setting in fixing setting valve; As triple channel threshold value change-over switch 5 is switched to the setting valve station 4 of floating, can be in unsteady setting valve station 4 set pressure carry out cooling, thereby controlled accurate more flexibly with loop rate of temperature fall.
Under accident conditions, when circuit pressure temperature transmitter 6 signals surpass triple channel threshold value change-over switch 5 threshold value, triple channel threshold value change-over switch 5 will automatically switch to first passage 2, through pi controller 8, setting valve aperture binary channels change-over switch 9, process, and through electropneumatic transducer 12, change the final aperture of controlling atmospheric dump valve 13 that realizes.Thus, under accident conditions, more accurately control a loop rate of temperature fall, and by the automatic cooling loop of the cooldown rate of 100 ℃/h, guarantee reactor safety, dependence operator intervention still less, the reliability of system is higher, and the ability of alleviation accident is stronger.
Here it should be noted that setting valve aperture binary channels change-over switch 9 can be switched by operator, this setting valve aperture binary channels change-over switch 9, normally in setting valve position, can switch to aperture position by opening adjuster 10 in the time of need to regulating aperture.
High card selection part is the product being overlapped to form by circuit that can buy on a market.
The control device of the utility model nuclear power plant airborne release system is not limited to above-mentioned embodiment, and those skilled in the art draw other embodiment according to the technical solution of the utility model, belongs to equally technological innovation scope of the present utility model.
Claims (6)
- The control device of 1.Yi Zhong nuclear power plant airborne release system, this control device comprises atmospheric dump valve control element (1), described atmospheric dump valve control element (1) is connected with the atmospheric dump valve (13) on airborne release pipeline, it is characterized in that: described atmospheric dump valve control element (1) comprises triple channel threshold value change-over switch (5), pi controller (8), setting valve aperture binary channels change-over switch (9) and the electropneumatic transducer (12) being connected successively.
- 2. the control device of nuclear power plant as claimed in claim 1 airborne release system, it is characterized in that: described triple channel threshold value change-over switch (5) is connected with three passages, can realize three-aisled switching, described three passages are respectively first passage (2), fixedly setting valve station (3) and unsteady setting valve station (4); Described triple channel threshold value change-over switch (5) is also connected with a circuit pressure temperature transmitter (6).
- 3. the control device of nuclear power plant as claimed in claim 2 airborne release system, it is characterized in that: described first passage (2) comprises temperature indicator (TI) (14), pressure indicator (7) and signal processing card part (15), described temperature indicator (TI) (14) is connected with described signal processing card part (15) respectively with pressure indicator (7); Described pressure indicator (7) is also connected with described pi controller (8).
- 4. the control device of nuclear power plant as claimed in claim 3 airborne release system, is characterized in that: described pressure indicator (7) comprises the high card selection part of pressure (19) and three pressure transducers that are arranged in parallel (16,17,18) that are connected with the high card selection part of described pressure (19).
- 5. the control device of nuclear power plant as claimed in claim 3 airborne release system, is characterized in that: described temperature indicator (TI) (14) comprises the high card selection part of temperature (23) and three temperature sensors that are arranged in parallel (20,21,22) that are connected with the high card selection part of described temperature (23).
- 6. the control device of the nuclear power plant's airborne release system as described in claim 1-5 any one, is characterized in that: described electropneumatic transducer (12) is connected with source of the gas (11) by gas supply line.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201420124055.9U CN203858871U (en) | 2013-05-30 | 2014-03-19 | Control device of nuclear power plant air emission system |
Applications Claiming Priority (3)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201320306301.8 | 2013-05-30 | ||
| CN201320306301 | 2013-05-30 | ||
| CN201420124055.9U CN203858871U (en) | 2013-05-30 | 2014-03-19 | Control device of nuclear power plant air emission system |
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| Publication Number | Publication Date |
|---|---|
| CN203858871U true CN203858871U (en) | 2014-10-01 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN201420124055.9U Expired - Lifetime CN203858871U (en) | 2013-05-30 | 2014-03-19 | Control device of nuclear power plant air emission system |
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105298556A (en) * | 2015-10-22 | 2016-02-03 | 中国核电工程有限公司 | Adjusting and controlling method for atmosphere air bleed valve of nuclear power plant |
| CN107068214A (en) * | 2017-05-09 | 2017-08-18 | 中广核研究院有限公司 | Nuclear power plant steam air tapping equipment and secondary circuit pressure method for releasing |
| WO2020113505A1 (en) * | 2018-12-05 | 2020-06-11 | 深圳中广核工程设计有限公司 | Safety-level functional control system and method for steam atmospheric emissions system of nuclear power plant |
-
2014
- 2014-03-19 CN CN201420124055.9U patent/CN203858871U/en not_active Expired - Lifetime
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105298556A (en) * | 2015-10-22 | 2016-02-03 | 中国核电工程有限公司 | Adjusting and controlling method for atmosphere air bleed valve of nuclear power plant |
| CN105298556B (en) * | 2015-10-22 | 2019-12-13 | 中国核电工程有限公司 | Regulation control method for atmospheric emission valve of nuclear power station |
| CN107068214A (en) * | 2017-05-09 | 2017-08-18 | 中广核研究院有限公司 | Nuclear power plant steam air tapping equipment and secondary circuit pressure method for releasing |
| CN107068214B (en) * | 2017-05-09 | 2024-03-26 | 中广核研究院有限公司 | Nuclear power plant steam atmosphere discharge device and two-loop pressure release method |
| WO2020113505A1 (en) * | 2018-12-05 | 2020-06-11 | 深圳中广核工程设计有限公司 | Safety-level functional control system and method for steam atmospheric emissions system of nuclear power plant |
| EP3904640A4 (en) * | 2018-12-05 | 2022-12-07 | China Nuclear Power Design Company Ltd. (Shenzhen) | Safety-level functional control system and method for steam atmospheric emissions system of nuclear power plant |
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| CX01 | Expiry of patent term |