CN110428919A - The design method of PWR nuclear power plant reactivity control strategy based on sign - Google Patents

The design method of PWR nuclear power plant reactivity control strategy based on sign Download PDF

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Publication number
CN110428919A
CN110428919A CN201910609005.7A CN201910609005A CN110428919A CN 110428919 A CN110428919 A CN 110428919A CN 201910609005 A CN201910609005 A CN 201910609005A CN 110428919 A CN110428919 A CN 110428919A
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China
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control strategy
sign
reactivity
accident
power plant
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CN110428919B (en
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杜宇
李力
孙涛
易珂
杨庆明
司天琪
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China Nuclear Power Engineering Co Ltd
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China Nuclear Power Engineering Co Ltd
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/001Computer implemented control
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/08Regulation of any parameters in the plant
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin

Abstract

The design method of the present invention relates to a kind of PWR nuclear power plant reactivity control strategy based on sign, comprising: (1) the neutron flux instrument based on reflection reactor core subcriticality classifies accident conditions according to the degree that reactor core subcriticality is lost;(2) the accident inventory that the control of reactor core reactivity needs to cope with is determined respectively;(3) reactive control-Strategy analysis is carried out, guarantees that control strategy can satisfy the process demand of most harsh accident conditions;(4) verification and validation is carried out to reactive control strategy;(5) final reactive control strategy is formed.The present invention is widely used in the PWR nuclear power plant of different heap-type, has universal applicability and envelope to the accident treatment of heteropathy, can guarantee the safety and validity of the control of nuclear power plant's reactivity.

Description

The design method of PWR nuclear power plant reactivity control strategy based on sign
Technical field
The invention belongs to nuclear power plant design technology fields, and in particular to a kind of PWR nuclear power plant reactivity based on sign The design method of control strategy.
Background technique
Depth defense is the safe design requirement that nuclear power plant design safety provides that (HAF) prosecutes to the end.Accident treatment rule The three lines of defence of Cheng Zuowei depth defense principle guarantees that reactor safety plays vital work to limitation accident development With.Sign guiding accident treatment strategy combines the advantages of event guiding both malfunction protocol and station guide malfunction protocol, with It is trunk that sign, which is oriented to accident treatment, provides and diagnoses more means countermeasures at many levels, emphasis grabs key security functionality, both can be in thing Therefore sign it is obvious when accident mitigation and processing quickly carried out using optimal recovery regulation by event guiding, and can begin Material not and accident or superposition accident when by key security functionality State Tree guide function restore directive/guide guarantee power plant respectively shield Barrier safety, to reach the smallest purpose of radioactivity that can be discharged into environment.Reactivity control is guarantee npp safety three big One of security function, it is ensured that reactor core it is subcritical controlled range be nuclear power plant control primary goal.
Nuclear power plant's complexity is higher, for PWR nuclear power plant, in addition to nuclear steam supply system and therrmodynamic system Outside, in order to ensure safety, several engineered safeguards features are also provided with.Such as consider various auxiliary systems and support system, nuclear power plant System quantity reach hundreds of.Sign guiding accident directive/guide reactivity control is related to a large amount of systems of nuclear power plant and equipment, and strategy is each A step is influenced each other and is associated with, and needs to determine based on scientific and reasonable design method analysis.
Summary of the invention
The design method of the object of the present invention is to provide a kind of PWR nuclear power plant reactivity control strategy based on sign, Classified according to mode of the degree of subcritical forfeiture to reactivity control, determine reactive control strategy respectively and verified true Its correctness is recognized, to guarantee the safety and validity of nuclear power plant's reactivity control.
Technical scheme is as follows: a kind of design side of the PWR nuclear power plant reactivity control strategy based on sign Method includes the following steps:
(1) the neutron flux instrument based on reflection reactor core subcriticality, the degree lost according to reactor core subcriticality is by thing Therefore operating condition is classified;
(2) according to the classification of step (1), the accident inventory that the control of reactor core reactivity needs to cope with is determined respectively;
(3) reactive control-Strategy analysis is carried out, guarantees that control strategy can satisfy the processing need of most harsh accident conditions It asks;
(4) verification and validation is carried out to reactive control strategy;
(5) final reactive control strategy is formed.
Further, the design method of the PWR nuclear power plant reactivity control strategy based on sign as described above, step (1) in, according to the degree of subcritical forfeiture, accident conditions are classified based on sign, comprising:
1) core power generates or have a possibility that core power generation;
2) reactor core shutdown margin is insufficient.
Further, the design method of the PWR nuclear power plant reactivity control strategy based on sign as described above, step (2) it in, is calculated according to fail- safe analysis, probability analysis and simulation, determines Analyses of Typical Accidents reactive for reactor core, In, described " 1) having core power to generate or have a possibility that core power generation " the corresponding Analyses of Typical Accidents includes:
A) fail the anticipated transient of emergency shut-down;
B) the excessive introducing operating condition of other positive reactivities.
Further, the design method of the PWR nuclear power plant reactivity control strategy based on sign as described above, step (3) in, worst operating condition progress analysis of strategies is controlled for reactivity and determine policy framework, while being determined by calculating analysis Related measure executes corresponding setting valve;In order to make control strategy can satisfy the demand of all accident conditions under the sign, need The mitigation strategy is analyzed to the inclusiveness for the typical condition of positive reactivity excessively introduced, such as cannot match or contain, is needed Accident treatment strategy is adjusted to match all typical conditions.
Further, the design method of the PWR nuclear power plant reactivity control strategy based on sign as described above, step (4) in, the correctness by carrying out written examination authentication policy to reactive control strategy is needed;It is also needed simultaneously by simulating allusion quotation The initial operating condition of type accident, is handled according to accident treatment strategy, the control effect of confirmation reactivity and other parameters, with confirmation Whether reactive control strategy meets design requirement, is such as unsatisfactory for redefining reactive control strategy.
Beneficial effects of the present invention are as follows: the PWR nuclear power plant reactivity provided by the present invention based on sign controls plan Design method slightly, is widely used in the PWR nuclear power plant of different heap-type.Severity of this method based on subcritical forfeiture Classify to sign, operator on the one hand can be made to define the severity of current subcritical forfeiture, so that it is determined that at accident On the other hand the successive operation order of reason can be directed to the operating condition of different subcritical forfeitures, carry out the processing plan of corresponding operating condition Analysis slightly, and the design of reactive control strategy is carried out respectively.The present invention is based on to the worst accident conditions of reactivity into Row strategy and definite value analysis, and the strategy is analyzed to the inclusiveness and matching of other typical conditions, plan is controlled for reactivity Design slightly has extensive implementable meaning.The design method ensure that the PWR nuclear power plant reactivity based on sign controls The safety and validity of strategy.
Detailed description of the invention
Fig. 1 is that the present invention is based on the reactive control strategy design flow diagrams of sign.
Specific embodiment
The present invention is described in detail below with reference to the accompanying drawings and embodiments.
Sign guiding accident directive/guide reactivity control is related to a large amount of systems of nuclear power plant and equipment, is carrying out nuclear power plant's reactivity When the design of control strategy, emphasis is needed to solve following problems:
Determination effectively monitors reactive information, and is carried out at classification according to the degree of subcritical forfeiture to accident sign Reason.
Based on the degree of subcritical forfeiture, determine for the analysis of accident sign can be used for alleviating and to control reactor core anti-respectively The control strategy of answering property.
Reactivity control for the PWR nuclear power plant based on sign, the accident for coping with heteropathy have extensively Applicability and envelope.
The verification method to reactive control strategy need to be established, and verifies whether the strategy meets the requirements.
For the above technical issues that need to address, the invention proposes a kind of advanced pressurized water reactor nuclear power plant based on sign The design method of reactive control strategy, method flow is as shown in Figure 1, specific method includes the following steps:
(1) the neutron flux instrument based on reflection reactor core subcriticality, the degree lost according to reactor core subcriticality is by thing Therefore operating condition is classified.
After reactor emergency shut-down, it is contemplated that neutron flux will quickly reduce, and be then reduced to just with a fixed rate Normal shutdown is horizontal.After a few minutes, decay heat of the reactor core heat production mainly from fission product, rather than nuclear fission itself.5% (by taking certain power plant as an example) rated power is bigger than the decay power that engineered safeguards features can be taken away, and shows greater than 5% rated power Operator needs to take an immediate action to prevent reactor core from damaging.Consider the influence to the subcritical forfeiture of reactor core, it can according to seriousness It is divided based on sign are as follows:
1) neutron flux > 5% has core power to generate or have a possibility that core power generation;
2) neutron flux≤5%, reactor core shutdown margin are insufficient.
(2) by taking " thering is core power to generate or have a possibility that core power generation " as an example, determine that reactor core reactivity controls needs The accident inventory of reply.
It is calculated according to fail- safe analysis, probability analysis and associated analog, depending on the II class operating condition event of generation, is existed A variety of anticipated transients (ATWS) for failing emergency shut-down.All ATWS transient states can all occur primary Ioops generation power with pass through This feature of the power mismatch that secondary circuit is taken away.This will lead to primary Ioops increasing temperature and pressure, until Doppler effect and moderator temperature Degree effect begins to decline core power.
There are also several situations will lead to " having core power to generate or have a possibility that core power generation ", the first is reactor Emergency shut-down is not thorough, it may be possible to because a part of control rod is not inserted into, or because some control rods are not inserted into bottom, but It is all not reach the degree that may be considered ATWS.Second is primary Ioops boron dilution, and the water source for injecting primary Ioops does not have in advance Have by correctly boronation, or injection is carried out to primary Ioops using wrong water source and will lead to primary Ioops boron dilution.Third Kind is primary Ioops sub-cooled, it may be possible to which, because secondary side release or SG are to dilutional hyponatremia, negative moderator temperature coefficient will Introduce positive reactivity.
Accordingly, it can be determined that Analyses of Typical Accidents reactive for reactor core.Include:
A) fail the anticipated transient of emergency shut-down;
B) the excessive introducing operating condition of other positive reactivities.
(3) reactive control-Strategy analysis
In order to which the accident conditions to the heteropathy sign are analyzed, should be divided first for worst operating condition Analysis, guarantees that control strategy can satisfy the process demand of most harsh accident conditions.For reactivity control worst operating condition into Row analysis of strategies determine policy framework, and determine that related measure executes corresponding setting valve by calculating analysis.Accident treatment What these setting valves applied in strategy depended on reaching required for strategy target to be achieved and each sub-step Target decides performing effectively for entire strategy, has great significance to maintaining npp safety to run.Meanwhile in order to make Control strategy can satisfy the demand of all accident conditions under the sign, it is also necessary to analyze the mitigation strategy to the mistake of positive reactivity The inclusiveness for spending the typical condition introduced, such as cannot match or contain, and need to be adjusted accident treatment strategy to match All typical conditions.
(4) reactive control strategy verification and validation
After completing reactive control strategy, need to carry out the work of verification and validation.It is verified as written audit policy just True property.It is identified through and is carried out using confirmation tool, simulate the initial operating condition of representative accident, handled according to accident treatment strategy, The control effect of confirmation reactivity and other parameters is such as unsatisfactory for confirming whether reactive control strategy meets design requirement Redefine reactive control strategy.
(5) final reactive control strategy is formed
Based on above-mentioned analysis and verifying and confirmation as a result, forming the reactive control strategy based on sign.
Embodiment
By taking certain PWR nuclear power plant as an example, plan is controlled to the advanced pressurized water reactor nuclear power plant reactivity of the invention based on sign The specific implementation of slightly design method is illustrated.
(1) the neutron flux instrument based on reflection reactor core subcriticality, the degree lost to reactor core subcriticality are divided Class is as follows:
Have core power to generate or have a possibility that core power generation: when power range power is greater than 5%, explanation, which has, splits Variable power generates, and when the intermediate quantity journey doubling time being greater than 0, fission power generates tendency.
Reactor core shutdown margin is insufficient: the source measuring range multiplication time is greater than 0.
(2) the accident inventory that the control of reactor core reactivity needs to cope with is determined.
It is illustrated by taking " thering is core power to generate or have a possibility that core power generation " accident conditions as an example, accident or operating condition Inventory are as follows:
1) fail the anticipated transient of emergency shut-down;
2) the excessive introducing of positive reactivity:
Part control rod is not inserted into;
Primary Ioops boron dilution;
Primary Ioops sub-cooled.
Wherein, the anticipated transient for failing emergency shut-down, which may cause primary Ioops superpressure or DNBR, to transfinite, " to have core power Generate or have a possibility that core power generation " worst operating condition in accident conditions.
(3) reactive control-Strategy analysis.
For failing the anticipated transient accident of emergency shut-down, needing the measure taken through analysis mainly includes reactor shutdown Driving, the shutdown of control rod gravity, steam turbine chaser, auxiliary feedwater starting, soluble poison injection (such as emergency reactor boron injection open Dynamic and reactor boron and water system control), steam generator water level control, isolation dilution tunnel, primary Ioops temperature adjust and Finally confirmation reactor is in subcritical state, and related measure is obtained by calculation and executes corresponding setting valve.Further analysis Fail the inclusiveness for the typical condition that the anticipated transient mitigation strategy of emergency shut-down excessively introduces other positive reactivities.
For " part control rod is not inserted into ", the mitigation strategy that the anticipated transient by failing emergency shut-down is taken, packet Reactor shutdown is included, dilution tunnel is isolated, the plan that primary Ioops temperature is adjusted in the shutdown of control rod gravity and soluble poison injection The accident can slightly be effectively relieved.It can be by not through analyzing to " primary Ioops boron dilution " and " primary Ioops sub-cooled " operating condition yet The anticipated transient mitigation strategy of energy emergency shut-down is contained.
(4) policy validation and confirmation are carried out.
1) correctness of paper audit authentication policy.
2) correctness of accident treatment strategy under Analyses of Typical Accidents is verified.
Verified and confirmation, shows that above-mentioned strategy can satisfy the requirement of accident treatment.
(5) final reactive control strategy is formed.
Based on above-mentioned analysis and verifying and confirmation as a result, completing the reactive control strategy based on sign.
Obviously, various changes and modifications can be made to the invention without departing from essence of the invention by those skilled in the art Mind and range.If in this way, belonging to the model of the claims in the present invention and its equivalent technology to these modifications and changes of the present invention Within enclosing, then the present invention is also intended to include these modifications and variations.

Claims (5)

1. a kind of design method of the PWR nuclear power plant reactivity control strategy based on sign, includes the following steps:
(1) the neutron flux instrument based on reflection reactor core subcriticality, the degree lost according to reactor core subcriticality is by accident work Condition is classified;
(2) according to the classification of step (1), the accident inventory that the control of reactor core reactivity needs to cope with is determined respectively;
(3) reactive control-Strategy analysis is carried out, guarantees that control strategy can satisfy the process demand of most harsh accident conditions;
(4) verification and validation is carried out to reactive control strategy;
(5) final reactive control strategy is formed.
2. the design method of the PWR nuclear power plant reactivity control strategy based on sign as described in claim 1, feature It is: in step (1), according to the degree of subcritical forfeiture, accident conditions is classified based on sign, comprising:
1) core power generates or have a possibility that core power generation;
2) reactor core shutdown margin is insufficient.
3. the design method of the PWR nuclear power plant reactivity control strategy based on sign as claimed in claim 2, feature It is: in step (2), is calculated according to fail- safe analysis, probability analysis and simulation, determines typical thing reactive for reactor core Therefore operating condition, wherein described " 1) thering is core power to generate or have a possibility that core power generation " the corresponding Analyses of Typical Accidents packet It includes:
A) fail the anticipated transient of emergency shut-down;
B) the excessive introducing operating condition of other positive reactivities.
4. the design method of the PWR nuclear power plant reactivity control strategy based on sign as described in claim 1, feature It is: in step (3), controls worst operating condition progress analysis of strategies for reactivity and determine policy framework, while passing through meter Point counting, which is analysed, determines that related measure executes corresponding setting valve;In order to make control strategy can satisfy all accident conditions under the sign Demand, need to analyze the mitigation strategy to the inclusiveness for the typical condition of positive reactivity excessively introduced, cannot such as match or Person is contained, and needs to be adjusted accident treatment strategy to match all typical conditions.
5. the design method of the PWR nuclear power plant reactivity control strategy based on sign as described in claim 1, feature It is: in step (4), needs the correctness by carrying out written examination authentication policy to reactive control strategy;It also needs simultaneously By simulating the initial operating condition of representative accident, handled according to accident treatment strategy, the control of confirmation reactivity and other parameters Effect is such as unsatisfactory for redefining reactive control strategy to confirm whether reactive control strategy meets design requirement.
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CN111755139A (en) * 2020-04-20 2020-10-09 中国核电工程有限公司 Design method of pressure vessel stack top exhaust control strategy under accident condition
CN113257448A (en) * 2021-04-21 2021-08-13 广东核电合营有限公司 Control method and equipment for nuclear power plant reactor extrapolation criticality
CN113362975A (en) * 2021-06-07 2021-09-07 中国核动力研究设计院 Method and system for dealing with accident of insufficient reactor core subcritical degree caused by nuclear power plant fault
CN113972019A (en) * 2020-07-23 2022-01-25 华龙国际核电技术有限公司 Nuclear power plant accident handling strategy generation method and device and electronic equipment

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CN111755139A (en) * 2020-04-20 2020-10-09 中国核电工程有限公司 Design method of pressure vessel stack top exhaust control strategy under accident condition
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CN111627584B (en) * 2020-04-30 2023-11-24 中国核电工程有限公司 Nuclear power plant symptom guide function recovery accident guide rule confirmation working condition selection method
CN113972019A (en) * 2020-07-23 2022-01-25 华龙国际核电技术有限公司 Nuclear power plant accident handling strategy generation method and device and electronic equipment
CN113972019B (en) * 2020-07-23 2024-04-16 华龙国际核电技术有限公司 Nuclear power plant accident handling strategy generation method and device and electronic equipment
CN113257448A (en) * 2021-04-21 2021-08-13 广东核电合营有限公司 Control method and equipment for nuclear power plant reactor extrapolation criticality
CN113257448B (en) * 2021-04-21 2024-04-19 广东核电合营有限公司 Control method and equipment for reactor extrapolation critical of nuclear power plant
CN113362975A (en) * 2021-06-07 2021-09-07 中国核动力研究设计院 Method and system for dealing with accident of insufficient reactor core subcritical degree caused by nuclear power plant fault

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