CN109712732A - A kind of manual diversified triggering method of nuclear power station engineered safeguards features - Google Patents
A kind of manual diversified triggering method of nuclear power station engineered safeguards features Download PDFInfo
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- CN109712732A CN109712732A CN201811589483.8A CN201811589483A CN109712732A CN 109712732 A CN109712732 A CN 109712732A CN 201811589483 A CN201811589483 A CN 201811589483A CN 109712732 A CN109712732 A CN 109712732A
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- 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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Abstract
The invention belongs to nuclear plant safety systems technology fields, specifically disclose a kind of manual diversified triggering method of nuclear power station engineered safeguards features: when common cause fault occurs in the safe I&C system in 4 weight redundant channels, there is exit passageway fault alarm in master control room control panel；Confirm reactor whether emergency shut-down, if reactor does not have automatic shutdown, manual shutdown；Manual diversified drive system operation button is set to be used；It alarms if there is origination event, indicates further accident conditions, diversified drive system manually need to be operated；Confirm accident pattern；Button in master control room control panel is operated according to accident pattern, diversification drive system triggers corresponding engineered safeguards features manually；It alarms and disappears such as origination event, indicate that accident conditions have been alleviated；The engineered safeguards features of reset trigger close diversified drive system manually.This method can prevent engineered safeguards features from can not operate due to safe I&C system common cause fault, guarantee the triggering of engineered safeguards features.
Description
Technical field
The invention belongs to nuclear plant safety systems technology fields, and in particular to a kind of nuclear power station engineered safeguards features it is manual
Diversified triggering method.
Background technique
Nuclear plant digital protects system to use traditional 4 channels, 2 species diversity framework, by reactor emergency shut-down system
System and Engineered safety feature actuation system (ESFAS) two parts are constituted.The driving principle of protection system can be divided into automatic trigger side
Formula and two kinds of manual triggering mode: automatic trigger mode passes through signal acquisition module circle collection parameters of technique process and is patrolled
Operation is collected, four independent operation results in channel generate trigger signal after 4 take 2 votings and are transmitted to driving module；Triggering manually
The manual trigger command of emergency shut-down is both transmitted to hardware driving also by hardwire by digitized software systems in mode
Module, and the manual trigger command of Engineered safety feature actuation system (ESFAS) is only by digitized software transmission to excellent
Select a kind of mode of output module.
Since nuclear power station engineered safeguards features are not independently of the triggering mode of computerization software, software common cause fault can
Reactor can be caused possibly can not to carry out waste heat export, prevent radioactive substance from the operation such as leaking.
Summary of the invention
For above-mentioned engineered safeguards features in the prior art not independently of the triggering mode of computerization software, software is total
Waste heat export possibly can not be carried out because failure may cause reactor, prevent radioactive substance from the technical problems such as leaking, the present invention
A kind of nuclear power station engineered safeguards features are provided, this method can prevent engineered safeguards features due to safe I&C system altogether for some reason
Hinder and can not operate, guarantees the manual diversification triggering of engineered safeguards features.
Realize the technical solution of the object of the invention:
A kind of manual diversified triggering method of nuclear power station Engineered safety feature actuation system, the specific steps of this method are such as
Under:
In step (1) nuclear power station unit station normal course of operation, when 4 weight redundant channels in safe I&C system occur altogether because
When failure, master control room control panel will appear all safe passageway system fault alarms；
Whether step (2) confirms reactor emergency shut-down, if because safe passageway system failure causes reactor not have
There is automatic shutdown, then carries out manual shutdown；
Step (3) enables manual diversified drive system operation button to be used；
Step (4) indicates if diversified drive system origination event alarm manually occurs in master control room control panel into one
Accident conditions are walked, need to operate diversified drive system manually；
Step (5) confirms the type of accident by the monitoring screen that master control room manipulates terminal；
Step (6) operates the button in master control room control panel according to accident pattern, is touched by manual diversified drive system
Send out engineered safeguards features corresponding；
Step (7) disappears if master control room control panel shows that diversified drive system origination event is alarmed manually, then it represents that
The accident conditions occurred in step (6) have been alleviated, at this point, resetting above-mentioned step by the reset button in master control room control panel
Suddenly all triggered engineered safeguards features in (6) close diversified drive system manually.
Common cause fault in the step (1) is software common cause fault.
Whether reactor emergency shut-down is confirmed by master control room control panel in the step (2).
The locking key in master control room control panel is opened in the step (3), so that diversification drive system behaviour manually
It is available to make button.
Accident pattern in the step (5) includes that reactor can not normal shutdown, primary Ioops coolant loss, steam
Generator dehydration, containment pressure limit, radioactive substance leaks, steam generator tube rupture, full factory are lost in containment
Electricity.
The step (6) if in accident pattern be reactor can not normal shutdown, trigger engineered safeguards features
Emergency boron injected system；If accident pattern is containment pressure limit, engineered safeguards features containment spray system is triggered,
And engineered safeguards features chemical reagent supply system is triggered according to severity of injuries；If accident pattern is primary Ioops coolant
It loses, then triggers engineered safeguards features low head injection system, and consider that triggering engineered safeguards features are high according to severity of injuries
Press safety injection system；If accident pattern be steam generator tube rupture, trigger engineered safeguards features steam generator to
Water segregation system and steam generator steam shielding system；If accident pattern is steam generator dehydration, ad hoc peace is triggered
Full facility steam generator emergency feedwater supply system；If accident pattern is that radioactive substance leaks in containment, trigger ad hoc
Safety devices Containment Isolation System；If accident pattern is full factory's power loss, engineered safeguards features Emergency diesel point is triggered
Grade band loading system.
If the accident pattern in the step (5) includes one or more, triggering accident class in step (6)
The corresponding one or more kinds of engineered safeguards features of type, if the diversification driving manually of master control room control panel in step (7)
The alarm of system origination event disappears, and indicates that all types of accident conditions occurred in step (6) have been alleviated, then resets at step
Suddenly all engineered safeguards features triggered in (6).
The beneficial technical effect of the present invention lies in: in protection system software common cause fault can occur for method of the invention
In the case of, ensure the manual hard triggering of following engineered safeguards features security function: emergency boron injected system, container spray system
System, chemical reagent supply system, High-pressure injection system, low head injection system, steam generator water supply shielding system, steam generation
Device emergency feedwater supply system, steam generator steam shielding system, Containment Isolation System and Emergency diesel classification band loading system.
Method of the invention has many advantages, such as that non-computer technology, high reliablity, system complexity are low, easy to implement, for other electricity
There is reference in the design pole of I&C system of standing reply software common cause fault.
Detailed description of the invention
Fig. 1 is a kind of manual diversified triggering method of nuclear power station Engineered safety feature actuation system provided by the present invention
Flow chart.
Specific embodiment
With reference to the accompanying drawings and examples to a kind of manual multiplicity of nuclear power station engineered safeguards features provided by the present invention
Change triggering method to be described in further detail.
As shown in Figure 1, a kind of manual diversification touching of nuclear power station Engineered safety feature actuation system provided by the present invention
Forwarding method, specific step is as follows for this method:
In step (1) nuclear power station unit station normal course of operation, when 4 weight redundant channels in safe I&C system occur altogether because
When failure, master control room control panel will appear all safe passageway system fault alarms.
For example, master control room control panel will appear all peaces when software common cause fault occur in 4 channels of safe I&C system
Full tunnel fault alarm.
Whether step (2) confirms reactor emergency shut-down by master control room control panel, if because safe passageway system
Failure causes reactor not have automatic shutdown, then carries out manual shutdown.
Step (3) opens the locking key in master control room control panel, so that diversification drive system (MASS) operates manually
Button is available.
Diversification drive system (MASS) operation button is available manually, that is, so that diversification drive system (MASS) manually
In operable state, prevent further derivative or superposition accident.
Step (4) indicates if diversified drive system (MASS) origination event alarm manually occurs in master control room control panel
There are further accident conditions, has needed to operate diversified drive system (MASS) manually.
Step (5) manipulates the type that terminal monitors picture confirms accident by master control room.
Accident is in the case that software fault occurs in safe I&C system, and some accidents for jeopardizing nuclear safety are derivative or are superimposed
Occur, accident pattern includes that reactor can not normal shutdown, containment pressure limit, primary Ioops coolant loss steam generator
Heat transfer tracheal rupture, steam generator dehydration, in containment radioactive substance leak, full factory's power loss etc..
Step (6) operates the button in master control room control panel according to accident pattern, passes through manual diversified drive system
(MASS) corresponding engineered safeguards features are triggered.
If accident pattern be reactor can not normal shutdown, trigger engineered safeguards features emergency boron injected system.Such as
Fruit accident pattern is containment pressure limit, then triggers engineered safeguards features containment spray system, and according to the serious journey of accident
Degree triggering engineered safeguards features chemical reagent supply system.If accident pattern is primary Ioops coolant loss, trigger ad hoc
Safety devices low head injection system, and triggering engineered safeguards features High-pressure injection system is considered according to severity of injuries.If
Accident pattern is steam generator tube rupture, then triggers engineered safeguards features steam generator water supply shielding system and steam
Steam of generator shielding system.If accident pattern is steam generator dehydration, engineered safeguards features steam generator is triggered
Emergency feedwater supply system.If accident pattern be containment in radioactive substance leak, trigger engineered safeguards features containment every
From system.If accident pattern is full factory's power loss, engineered safeguards features Emergency diesel classification band loading system is triggered.
Step (7) disappears if master control room control panel shows that diversified drive system (MASS) origination event is alarmed manually,
Then indicate that the accident conditions occurred in step (6) have been alleviated, at this point, resetting by the reset button in master control room control panel
All triggered engineered safeguards features in above-mentioned steps (6) close diversified drive system (MASS) manually.
When origination event, which is alarmed, to disappear, mean that all accidents all and be controllable, this when needs to be reset above-mentioned
All triggered engineered safeguards features, prevent overprotection from causing damages in step (6).
For example, the accident pattern in step (5) includes that all accident pattern reactors can not normal shutdown, containment pressure
Transfinite, primary Ioops coolant loss steam generator tube rupture, steam generator dehydration, in containment outside radioactive substance
It lets out, full factory's power loss, then triggering all engineered safeguards features emergency boron injected systems, containment spray system, chemistry in step (6)
Agent delivery system, High-pressure injection system, low head injection system, steam generator water supply shielding system, steam generator emergency
Water supply system, steam generator steam shielding system, Containment Isolation System and Emergency diesel classification band loading system；If main
Controlling room control panel, diversified drive system (MASS) origination event alarm disappears manually, indicates all classes occurred in step (6)
The accident conditions of type have been alleviated, then reset at all engineered safeguards features emergency boron injection system triggered in step (6)
System, containment spray system, chemical reagent supply system, High-pressure injection system, low head injection system, steam generator water supply every
From system, steam generator emergency feedwater supply system, steam generator steam shielding system, Containment Isolation System and emergency diesel-oil
Machine classification band loading system.
For example, the accident pattern in step (5) be only reactor can not normal shutdown when, if master control room control panel is manual
Diversified drive system (MASS) origination event alarm disappears, then it represents that the reactor occurred in step (6) can not normal shutdown
Accident conditions have been alleviated, then the engineered safeguards features emergency boron injected system of reset trigger.
For example, when the accident pattern in step (5) is only containment pressure limit accident, if master control room control panel is manual
Diversified drive system (MASS) origination event alarm disappears, then it represents that the containment pressure limit accident occurred in step (6)
Operating condition has been alleviated, then the engineered safeguards features containment spray system and chemical reagent supply system of reset trigger.
For example, when the accident pattern in step (5) is only primary Ioops coolant loss, if master control room control panel is more manually
The alarm of sample drive system (MASS) origination event disappears, then it represents that the primary Ioops coolant loss accident occurred in step (6)
Operating condition has been alleviated, then the engineered safeguards features low head injection system and High-pressure injection system of reset trigger.
For example, when the accident pattern in step (5) is only steam generator tube rupture, if master control room control panel hand
Dynamic diversification drive system (MASS) origination event alarm disappears, then it represents that the steam generator heat-transfer pipe occurred in step (6)
Break accident operating condition has been alleviated, then the engineered safeguards features steam generator water supply shielding system of reset trigger.
For example, when the accident pattern in step (5) is only steam generator dehydration, if master control room control panel is various manually
Change the alarm of drive system (MASS) origination event to disappear, then it represents that the steam generator loss of-coolant accident (LOCA) operating condition occurred in step (6)
It has been alleviated that, then the engineered safeguards features steam generator emergency feedwater supply system of reset trigger.
For example, when the accident pattern in step (5) is only that radioactive substance leaks in containment, if master control room control panel
The alarm of diversification drive system (MASS) origination event disappears manually, then it represents that radioactivity in the containment occurred in step (6)
The substance accident conditions that leak have been alleviated, then the engineered safeguards features Containment Isolation System of reset trigger.
For example, when the accident pattern in step (5) is only full factory's power loss, if the diversification driving manually of master control room control panel
The alarm of system (MASS) origination event disappears, and indicates that the full factory's power loss accident conditions occurred in step (6) have been alleviated, then resets
The engineered safeguards features Emergency diesel classification band loading system of triggering.
The present invention is explained in detail above in conjunction with drawings and examples, but the present invention is not limited to above-mentioned implementations
Example, within the knowledge of a person skilled in the art, can also make without departing from the purpose of the present invention
Various change out.The content being not described in detail in the present invention can use the prior art.
Claims (7)
1. a kind of manual diversified triggering method of nuclear power station Engineered safety feature actuation system, which is characterized in that this method
Specific step is as follows:
In step (1) nuclear power station unit station normal course of operation, when common cause fault occurs in the safe I&C system in 4 weight redundant channels
When, master control room control panel will appear all safe passageway system fault alarms；
Whether step (2) confirms reactor emergency shut-down, if because safe passageway system failure causes reactor without certainly
Dynamic shutdown, then carry out manual shutdown；
Step (3) enables manual diversified drive system operation button to be used；
Step (4) indicates further thing if diversified drive system origination event alarm manually occurs in master control room control panel
Therefore operating condition, need to operate diversified drive system manually；
Step (5) confirms the type of accident by the monitoring screen that master control room manipulates terminal；
Step (6) operates the button in master control room control panel according to accident pattern, passes through manual diversified drive system triggering pair
The engineered safeguards features answered；
Step (7) disappears if master control room control panel shows that diversified drive system origination event is alarmed manually, then it represents that step
(6) accident conditions occurred in have been alleviated, at this point, being resetted above-mentioned steps (6) by the reset button in master control room control panel
In all triggered engineered safeguards features, close diversified drive system manually.
2. a kind of manual diversified triggering method of nuclear power station Engineered safety feature actuation system according to claim 1,
It is characterized by: the common cause fault in the step (1) is software common cause fault.
3. a kind of manual diversified triggering method of nuclear power station Engineered safety feature actuation system according to claim 2,
It is characterized by: confirming reactor whether emergency shut-down by master control room control panel in the step (2).
4. a kind of manual diversified triggering method of nuclear power station Engineered safety feature actuation system according to claim 3,
It is characterized by: the locking key in master control room control panel is opened in the step (3), so that diversification drive system manually
Operation button is available.
5. a kind of manual diversified triggering method of nuclear power station Engineered safety feature actuation system according to claim 4,
It is characterized by: the accident pattern in the step (5) include reactor can not normal shutdown, primary Ioops coolant loss,
Steam generator dehydration, containment pressure limit, radioactive substance leaks, is steam generator tube rupture, complete in containment
Factory's power loss.
6. a kind of manual diversified triggering method of nuclear power station Engineered safety feature actuation system according to claim 5,
It is characterized by: the step (6) if in accident pattern be reactor can not normal shutdown, trigger ad hoc safety and set
Apply emergency boron injected system；If accident pattern is containment pressure limit, engineered safeguards features container spray system is triggered
System, and engineered safeguards features chemical reagent supply system is triggered according to severity of injuries；If accident pattern is that primary Ioops are cold
But agent is lost, then triggers engineered safeguards features low head injection system, and consider that triggering ad hoc safety sets according to severity of injuries
Apply High-pressure injection system；If accident pattern is steam generator tube rupture, engineered safeguards features steam generation is triggered
Device water supply shielding system and steam generator steam shielding system；If accident pattern is steam generator dehydration, triggering is special
If safety devices steam generator emergency feedwater supply system；If accident pattern is that radioactive substance leaks in containment, trigger
Engineered safeguards features Containment Isolation System；If accident pattern is full factory's power loss, engineered safeguards features emergency diesel-oil is triggered
Machine classification band loading system.
7. a kind of manual diversified triggering method of nuclear power station Engineered safety feature actuation system according to claim 6,
It is characterized by: triggering thing in step (6) if the accident pattern in the step (5) includes one or more
Therefore the corresponding one or more kinds of engineered safeguards features of type, if master control room control panel is diversified manually in step (7)
The alarm of drive system origination event disappears, and indicates that all types of accident conditions occurred in step (6) have been alleviated, then resets
Triggered all engineered safeguards features in step (6).
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Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110689973A (en) * | 2019-09-18 | 2020-01-14 | 上海电力大学 | Nuclear power station primary circuit pressure reduction control method under heat transfer pipe fracture accident |
| CN111681794A (en) * | 2020-06-19 | 2020-09-18 | 中国核动力研究设计院 | Full-range SGTR accident handling method and system for pressurized water reactor nuclear power plant |
| CN112016185A (en) * | 2020-07-06 | 2020-12-01 | 中国核电工程有限公司 | Design method for commissioning mode of accident handling system of nuclear power plant |
| CN113593739A (en) * | 2021-07-22 | 2021-11-02 | 中国核动力研究设计院 | Control method for dealing with water supply flow loss accident of nuclear power plant |
| CN113782241A (en) * | 2021-08-25 | 2021-12-10 | 苏州热工研究院有限公司 | Nuclear power plant operation control system and method under terrorist attack background |
| WO2023020635A1 (en) * | 2022-03-09 | 2023-02-23 | 深圳中广核工程设计有限公司 | Automatic low-pressure full-speed cooling method and system for nuclear power plant unit |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103400623A (en) * | 2013-07-30 | 2013-11-20 | 中广核工程有限公司 | Protection method and system for digitalized instrument control diversity of nuclear power station |
| CN107437345A (en) * | 2016-05-27 | 2017-12-05 | 江苏核电有限公司 | A kind of nuclear plant digital safety devices drive system training test platform |
| US20180190395A1 (en) * | 2016-12-30 | 2018-07-05 | Nuscale Power, Llc | Nuclear Reactor Protection Systems and Methods |
-
2018
- 2018-12-25 CN CN201811589483.8A patent/CN109712732A/en active Pending
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103400623A (en) * | 2013-07-30 | 2013-11-20 | 中广核工程有限公司 | Protection method and system for digitalized instrument control diversity of nuclear power station |
| CN107437345A (en) * | 2016-05-27 | 2017-12-05 | 江苏核电有限公司 | A kind of nuclear plant digital safety devices drive system training test platform |
| US20180190395A1 (en) * | 2016-12-30 | 2018-07-05 | Nuscale Power, Llc | Nuclear Reactor Protection Systems and Methods |
Non-Patent Citations (2)
| Title |
|---|
| 祁勋等: "核电站保护***多样化手动驱动***设计", 《核电子学与探测技术》 * |
| 穆海洋等: "田湾核电站反应堆保护***多样化的研究", 《核安全》 * |
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110689973A (en) * | 2019-09-18 | 2020-01-14 | 上海电力大学 | Nuclear power station primary circuit pressure reduction control method under heat transfer pipe fracture accident |
| CN110689973B (en) * | 2019-09-18 | 2023-04-28 | 上海电力大学 | Nuclear power station primary loop depressurization control method under heat transfer pipe rupture accident |
| CN111681794A (en) * | 2020-06-19 | 2020-09-18 | 中国核动力研究设计院 | Full-range SGTR accident handling method and system for pressurized water reactor nuclear power plant |
| CN112016185A (en) * | 2020-07-06 | 2020-12-01 | 中国核电工程有限公司 | Design method for commissioning mode of accident handling system of nuclear power plant |
| CN113593739A (en) * | 2021-07-22 | 2021-11-02 | 中国核动力研究设计院 | Control method for dealing with water supply flow loss accident of nuclear power plant |
| CN113782241A (en) * | 2021-08-25 | 2021-12-10 | 苏州热工研究院有限公司 | Nuclear power plant operation control system and method under terrorist attack background |
| CN113782241B (en) * | 2021-08-25 | 2023-05-12 | 苏州热工研究院有限公司 | Nuclear power plant operation control system and method in terrorist attack background |
| WO2023020635A1 (en) * | 2022-03-09 | 2023-02-23 | 深圳中广核工程设计有限公司 | Automatic low-pressure full-speed cooling method and system for nuclear power plant unit |
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