CN110444300B - Method for designing nuclear power plant reactor core cooling function control strategy based on symptoms - Google Patents
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- 238000001816 cooling Methods 0.000 title claims abstract description 210
- 208000024891 symptom Diseases 0.000 title claims abstract description 41
- 238000000034 method Methods 0.000 title claims abstract description 40
- 238000011217 control strategy Methods 0.000 title claims abstract description 33
- 238000013461 design Methods 0.000 claims abstract description 47
- 238000012163 sequencing technique Methods 0.000 claims abstract description 3
- 238000004458 analytical method Methods 0.000 claims description 26
- 238000004364 calculation method Methods 0.000 claims description 22
- 238000004088 simulation Methods 0.000 claims description 19
- 238000012795 verification Methods 0.000 claims description 15
- 238000012512 characterization method Methods 0.000 claims description 9
- 238000011156 evaluation Methods 0.000 claims description 6
- 230000008859 change Effects 0.000 claims description 5
- 230000002159 abnormal effect Effects 0.000 claims description 4
- 238000010606 normalization Methods 0.000 claims description 4
- 238000011002 quantification Methods 0.000 claims 1
- 238000011084 recovery Methods 0.000 abstract description 4
- 230000000694 effects Effects 0.000 description 4
- 238000012986 modification Methods 0.000 description 3
- 230000004048 modification Effects 0.000 description 3
- 238000012545 processing Methods 0.000 description 3
- 238000012300 Sequence Analysis Methods 0.000 description 2
- 230000006872 improvement Effects 0.000 description 2
- 238000013139 quantization Methods 0.000 description 2
- 238000010200 validation analysis Methods 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 230000004075 alteration Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000007812 deficiency Effects 0.000 description 1
- 238000012938 design process Methods 0.000 description 1
- 238000007599 discharging Methods 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 238000013486 operation strategy Methods 0.000 description 1
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- 239000002918 waste heat Substances 0.000 description 1
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/001—Computer implemented control
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
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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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- 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
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention relates to a design method of a nuclear power plant reactor core cooling function control strategy based on symptoms, which comprises the steps of (1) analyzing the reactor core cooling symptom limit value, determining an instrument combination theta for representing insufficient reactor core cooling, and obtaining the limit value requirement of the instrument reading in the reactor core cooling symptom instrument combination theta; (2) determining a list of incidents in which core cooling is challenged; (3) Analyzing a core cooling mode of a nuclear power plant, determining a core cooling mode set omega, and determining an optimal core cooling mode sequence according to comprehensive cooling capacity sequencing of the core cooling modes; (4) verifying and adjusting the reactor core cooling mode sequence; (5) And obtaining core cooling function control strategies designed for the nuclear power units with different technical characteristics. According to the invention, the optimal symptom-oriented critical safety function core insufficient cooling recovery strategy can be obtained according to different nuclear power unit design characteristics, and the advancement and safety of the core insufficient cooling recovery strategy are better reflected.
Description
Technical Field
The invention belongs to the technical field of nuclear power plant design, and particularly relates to a design method of a nuclear power plant reactor core cooling function control strategy based on symptoms.
Background
The nuclear power plant has complex design, various types of systems and equipment are involved, the number of initial causes which can cause accidents is huge, and the number of the initial causes is huge if the corresponding strategies are respectively formulated for the nuclear power plant. The symptom guiding method accident regulation realizes the purposes of controlling and relieving the accident result by controlling the key safety functions of the affected nuclear power plant after the accident occurs, can effectively treat complex working conditions and superimposed accidents, and is the most widely applied advanced accident treatment method internationally. Compared with the accident regulation system of the simple event guiding method, the accident regulation system of the symptom guiding method increases the depth defending thickness of the regulation and can more perfectly ensure the nuclear safety of the power plant. The reactor core cooling function is taken as one of important key safety functions of the nuclear power plant, the control and recovery strategy is an important component part of the symptom guide method accident regulation, and whether the design of the reactor core cooling function reasonably directly influences the rationality and rapidity of accident handling under the condition that the symptom guide method accident regulation reactor core is insufficiently cooled or the working condition is lost.
There is often a large system design difference between different reactor types of a nuclear power plant, so that a core cooling function control strategy suitable for the design characteristics of the different reactor types of the nuclear power plant needs to be determined according to the respective design characteristics of the different reactor types of the nuclear power plant. On the other hand, even for different units of the same stack type, due to the continuous improvement of the unit design, the system design and the function change can be caused, so that the control and alleviation design of the core cooling function of the unit is changed, and the core cooling control strategy framework and the design of the design fixed value are influenced. And the operation strategy of the unit is determined by combining the design characteristics analysis of the improved unit, so that the unit can be ensured to rapidly and accurately treat accidents. The symptom-oriented accident guidance core cooling function control strategy relates to a large number of systems and equipment of a nuclear power plant, and all steps of the strategy are mutually influenced and associated and need to be analyzed and determined based on a scientific and reasonable design method.
Disclosure of Invention
The invention aims to provide a design method of a critical safety function-core cooling function control strategy of an accident nuclear power plant based on symptoms, so as to obtain an optimal symptom-oriented critical safety function core cooling deficiency recovery strategy according to different nuclear power unit design characteristics, and better embody the advancement and safety of the emergency nuclear power plant.
The technical scheme of the invention is as follows: a design method of a nuclear power plant reactor core cooling function control strategy based on symptoms comprises the following steps:
(1) Performing core cooling symptom limit value analysis, and determining an instrument combination theta for representing insufficient core cooling to obtain a limit value requirement of instrument readings in the core cooling symptom instrument combination theta;
(2) Determining a list of incidents in which core cooling is challenged;
(3) Analyzing a core cooling mode of a nuclear power plant, determining a core cooling mode set omega, and determining an optimal core cooling mode sequence according to comprehensive cooling capacity sequencing of the core cooling modes;
(4) Verifying and adjusting the sequence of the cooling modes of the reactor core determined in the step (3) aiming at the accident conditions in the accident list of which the cooling of the reactor core is challenged determined in the step (2);
(5) A final core cooling function control strategy is determined.
Further, in the design method of the nuclear power plant core cooling function control strategy based on the symptoms, in the step (1), the core cooling key symptom representation is determined according to the design characteristics of the nuclear power plant, the core physics and the thermal hydraulic simulation calculation and the experimental result, the instruments representing the physical quantities are determined according to the abnormal physical quantity occurring when the core is insufficiently cooled, and the instrument combination theta for representing the core is further determined.
In step (1), a function set of the unit safety criterion requirement parameter and the meter reading is established by analyzing a change relation of the unit safety criterion requirement parameter and the meter reading, and the limit value requirement of the meter reading in the reactor core cooling characterization sign meter combination theta is obtained according to the corresponding function relation and the limiting range of the reactor core cooling critical sign characterization in the unit safety criterion.
In step (2), according to the relevant accident list concerned and required by the legal standard and the nuclear security department, the accident list which is challenged by the unit for core cooling is determined by combining the safety analysis and the relevant simulation calculation of the accidents in all accident lists in the nuclear power plant design, so that the accident condition requiring core cooling analysis is determined.
Further, in the method for designing a control strategy of a core cooling function of a nuclear power plant based on symptoms as described above, in the step (3), the cooling capacity of each core cooling mode in the core cooling mode set Ω is analyzed and the reliability of each core cooling mode is analyzed by the core physical and thermal hydraulic simulation calculation, the sub-functional capacity of each core cooling mode in the core cooling mode set Ω is analyzed and quantization is completed, normalization processing is performed as a specific numerical value as a sub-functional capacity evaluation number, and the weighting factors of each sub-function are determined and normalization processing is completed based on the safety and economical targets of the nuclear power plant; and combining the sub-function capacity evaluation number of each core cooling mode and the corresponding sub-function weight factors, quantitatively determining to obtain the comprehensive cooling capacity of each core cooling mode, and determining the optimal core cooling mode sequence according to the comprehensive cooling capacity sequence of the core cooling modes.
Furthermore, in the step (3), the setting value requirement to be met by the execution of the relevant core cooling measures in each core cooling mode is determined through calculation and analysis, so that the core cooling based on the core cooling mode can ensure that the meter reading in the core cooling characterization sign meter combination theta meets the limit value requirement.
Further, in the method for designing a control strategy of a nuclear power plant core cooling function based on symptoms as described above, in the step (4), the verification and adjustment modes are as follows:
(4-1) verifying whether the single core cooling mode meets the requirement of the meter reading limit value, if not, re-determining the core cooling mode according to the unit design and the core working condition simulation calculation in the step (3);
(4-2) verifying whether the combination of failure of one core cooling mode in the core cooling mode sequence stack meets the requirement of the meter reading limit value, if not, re-designing according to the unit, combining core working condition simulation calculation, and returning to the step (3) to re-determine the core cooling mode;
and (4-3) performing human factor verification, determining whether the human factor meets the requirements of the design criteria, and if not, modifying according to the verification result until the requirements are met.
The beneficial effects of the invention are as follows:
1. the invention is suitable for different reactor types including pressurized water reactor nuclear power plants, and provides a design method for developing a reactor core cooling function relieving strategy in the accident regulations of the symptom guide method of the different reactor types;
2. the reactor core cooling function relieving strategy designed according to the method can effectively cover the accident regulation coverage range of the nuclear power plant, and ensures that no corresponding reactor core cooling function relieving strategy exists under certain accident working conditions;
3. according to the invention, a relation function set which is established based on the reactor core cooling symptom and corresponds to the instrument and the safety criterion is provided for the first time, a reactor core cooling instrument limit value set is provided for the first time from the perspective of overall operation, multidimensional information is provided for an operator to monitor reactor core cooling, and the risk of human factor judgment errors is reduced;
4. the invention provides a method for determining the comprehensive capacity of the reactor core cooling mode by adopting the sub-function weight factors and sub-function priority analysis for the first time, ensures that the analysis range is comprehensive in the design of the function relief strategy, and the analysis conclusion can provide reference for further improvement of the unit design;
5. the reactor core cooling function relieving strategy designed according to the method provides an optimal operation sequence for operators in accident handling, and avoids accident handling delay caused by the fact that operators execute relieving sequences with lower reliability in the accident handling process.
Drawings
FIG. 1 is a flow chart of a method of designing a symptom-based nuclear power plant core cooling function control strategy of the present invention.
Detailed Description
The present invention will be described in detail with reference to the accompanying drawings and examples.
The design of a nuclear power plant is cumbersome, involving a large number of systems and equipment, which may be very large in the number of initial causes of the accident. The symptom guiding method realizes the control of the state of the unit through controlling and relieving the key safety function, so the control and relieving of the key safety function is one of the characteristics of the symptom guiding method accident handling rules, and the corresponding relieving and controlling strategy is crucial to the accident handling effect of the nuclear power plant. The reactor core cooling is used as a key function closely related to the safety of the nuclear power plant, a control strategy of the reactor core cooling relates to a large number of system equipment and functions of the nuclear power plant, and the following problems need to be solved in the design process of the control strategy:
the accident conditions which threaten the cooling safety of the reactor core are numerous, and the conditions need to be analyzed to determine the affected sub-functions and the corresponding symptoms. And determining information for effectively monitoring the core cooling, and determining the relation between the unit safety criterion parameter and the core cooling characterization instrument reading, wherein a proper analysis method needs to be found out.
The nuclear power plant system is complex in composition, various in system function, and capable of analyzing and determining unit safety functions for relieving and controlling core cooling, including corresponding systems and equipment, so as to obtain a core cooling mode set.
When the core cooling control strategy is manufactured, various factors such as cooling capacity, safety level, availability and the like of each core cooling mode are needed to be considered, a proper method is needed to analyze the system and the equipment, various factors are comprehensively considered, the comprehensive analysis range is ensured, and the optimal control strategy for core cooling under accidents is determined.
A verification method for the core cooling control strategy needs to be established, and whether the strategy meets the requirements is verified.
In order to solve the problems, the invention provides a scientific and reasonable reactor core cooling function control strategy design method. Based on the unit design and the core working condition simulation calculation, a relation function set corresponding to meters and safety criteria is established through core cooling symptom analysis, a core cooling mode sequence is determined according to the weight all-round analysis of the unit core cooling mode, and a series of verification is carried out to obtain the core cooling function control strategy aiming at the nuclear power unit design with different technical characteristics.
The specific method flow is shown in figure 1, and comprises the following steps:
(1) Core cooling symptom limit analysis
Based on design characteristics of nuclear power plant, reactor core physics and thermal hydraulic simulation calculationAnd experimental results, determining core cooling key sign characterization (such as a hot spot factor Y, and the like), determining meters for representing abnormal physical quantities (such as system temperature, and the like) when the core is insufficiently cooled, and further determining meter combinations theta [ a, b, c … … ] for representing the core cooling shortage]. Analyzing the change relation between the unit safety criterion requirement parameter (such as a hot spot factor and the like) and the meter reading, and establishing a function set Y- { F of the unit safety criterion requirement parameter and the meter reading A (X)，F B (X)，F C (X) … … }. And according to the limiting range of the core cooling key sign representation in the unit safety standard and the corresponding functional relation, obtaining the limit value requirement of the meter reading in the core cooling key sign meter combination theta.
(2) Determining a list of incidents for which core cooling is challenging
According to the rule standard and the related accident list concerned and required by the nuclear safety authorities, in combination with the design of the nuclear power plant, the accident list which is challenging for cooling the reactor core of the unit can be determined through the safety analysis and related simulation calculation of accidents in all accident lists.
(3) Core cooling function sequence analysis
Based on the nuclear power plant design, the core cooling patterns of the nuclear power plant are analyzed to determine a core cooling pattern set Ω [ A, B, C … … ]. Through core physics and thermodynamic hydraulic simulation calculation, the cooling capacity of each core cooling mode in omega is analyzed, and the reliability of each core cooling mode is analyzed, wherein the functions comprise cooling effect, safety grading, redundancy, reliability, functional positioning and the like. Analyzing and quantifying the sub-function capacity of each core cooling mode in omega, evaluating and scoring the capacity of each sub-function of the core cooling mode, and normalizing the values into specific values { A [ x1, x2, x3 … … ], B [ y1, y2, y3 … … ], C [ z1, z2, z3 … … ] … … }, for example, x1, x2, x3 … … are quantized values representing the sub-function capacity of the core cooling mode A. The weight factors of the sub-functions are determined based on the safety and economical targets of the power plant, and the normalization processing [ P1, P2, P3 … … ] is completed, wherein the weight factors are determined based on the safety and economical targets of the nuclear power plant according to the functional requirements of the power plant on the sub-functions. The method can comprise a safety weight factor and an economic weight factor, wherein the safety weight factor is used for quantifying the effect and speed of the function on accident alleviation, and the economic weight factor is used for quantifying the influence on the operation of the unit after the function is used, whether the equipment is reusable or not and other factors. And after combining the sub-function capacity evaluation number of each reactor core cooling mode and the corresponding sub-function weight factors, the comprehensive cooling capacity of each reactor core cooling mode can be quantitatively determined. And determining an optimal reactor core cooling mode sequence according to the comprehensive cooling capacity sequence of the reactor core cooling modes. Meanwhile, the setting value requirements which are required to be met by the execution of relevant core cooling measures in each core cooling mode are determined through calculation and analysis, so that the core cooling based on the mode can ensure that the meter readings in the core cooling characterization sign meter combination theta meet the limit value requirements.
(4) Policy validation and adjustment
And verifying the determined core cooling sequence based on the core cooling analysis working condition list of the unit safety requirements. The verification comprises the following contents:
verifying whether the single core cooling mode meets the requirement of the meter reading limit value, if not, re-determining the core cooling mode according to the unit design and the core working condition simulation calculation in the step (3).
Verifying whether the combination of failure of one of the core cooling modes is overlapped with the requirement of the meter reading limit value, if not, re-determining the core cooling mode in the step (3) according to the unit design and combining the core working condition simulation calculation.
Finally, human factor verification is needed, whether human factor factors such as operation time, task allocation, operator compatibility and the like meet the design criterion requirement is determined, and if not, modification is performed according to a verification result until the requirement is met.
(5) Determining core cooling function control strategy
After verification of the symptom-based advanced nuclear power plant core cooling control strategy is completed, a final core cooling function control strategy is formed.
Examples
Taking LOCA, FLB, SGTR accident conditions as an example, the specific implementation mode of the method is described:
(1) Core cooling symptom limit analysis
According to the simulation calculation results of the design characteristics of the nuclear power plant and the core working condition, analyzing the symptoms of the insufficient cooling function of the core, wherein the physical quantity of the abnormal phenomenon when the cooling of the core is insufficient through analysis comprises: parameter a-core outlet temperature (corresponding meters are Tco1, tco2, tco 3), parameter B-main system hot pipe section temperature (Thl 1, thl2, thl 3), and parameter C-pressure vessel level (Lv 1, lv 2). Analysis determines that the change relation function set of the core cooling control target core hot spot factor Y and meter reading is F respectively A (Tco1，Tco2，Tco3)，F B (Thl1，Thl2，Thl3)，F C (Lv 1, lv 2), which are well known in the art. Y is in the range of R in the unit safety standard, and according to the relation function of Y and meter reading, the corresponding meter A reading limit value range is obtained and is R A The reading limit value range of the instrument B is R B The reading limit value range of the instrument C is R C If the readings of the reactor core cooling characterization instrument group exceed the limit value, the parameter Y is beyond the safety standard range of the unit.
(2) Determining a list of incidents for which core cooling is challenging
According to the regulation standard and related accident List-1 concerned and required by the nuclear security authorities, combining the design of the power plant, and obtaining the accident with the challenge of core cooling in the List-1 through the security analysis and related simulation calculation of the accident in the accident List [ LOCA, FLB, SGTR ], namely forming the accident List with the challenge of core cooling of the power plant.
(3) Core cooling function sequence analysis
According to the design of a nuclear power plant, the core cooling mode of the power plant is obtained by: mode 1-emergency core cooling, mode 2-evaporator atmospheric exhaust+auxiliary water supply, mode 3-residual heat removal system, and determining core cooling mode set Ω as [ mode 1, mode 2, mode 3]. Through core working condition simulation calculation, the cooling capacity of each core cooling mode in omega is analyzed, the reliability of each core cooling mode is analyzed, and the considered sub-functions comprise cooling effect, reliability and redundancy. The sub-function evaluation numbers of the respective core cooling systems are { system 1[0.3,0.5,0.2], system 2[0.5,0.1,0.4], system 3[0.1,0.4,0.5] }, and the weight factors of the respective sub-functions are [0.5,0.3,0.2], so that the total cooling capacity of the respective core cooling systems is calculated as [0.34,0.36,0.27], and the sub-function quantization values of the respective core cooling systems are multiplied by the corresponding weight factors and added, whereby the optimal core cooling system sequence is determined as [ system 2, system 1, system 3] (not actual values, but only by way of example). The calculation and analysis determine setting value requirements to be met by the execution of relevant core cooling measures in each mode, so that the core cooling based on the mode can ensure that the meter reading in the step (1) meets the limit value requirements.
(4) Policy validation and adjustment
And (3) verifying the determined reactor core cooling sequence under the [ LOCA, FLB, SGTR ] accident condition in the accident list with the challenged reactor core cooling in the step (2).
And (3) verifying a single core cooling mode, wherein in the case of [ LOCA, FLB, SGTR ] accidents, each meter reading listed in the step (1) can meet the limit requirement, and in the case of mode 3, the limit requirement cannot be met, so that the core cooling mode needs to be determined again according to the power plant design, for example, the mode 3 is modified into a mode 3-passive waste heat discharging system or other modes, until the requirement is met.
And then verifying whether the combination of failure of one of the core cooling modes superimposed by the core cooling mode sequence meets the requirement. Through verification that the superposition mode 2 of the reactor core cooling mode sequence fails under the LOCA accident, each meter reading listed in the step (1) cannot meet the limit requirement, so that the reactor core cooling mode sequence needs to be determined by re-analysis according to the design of the power plant, for example, the mode 2 is modified to be mode 2, until the requirement is met. Finally, a single core cooling mode is obtained, and the combination of core cooling mode sequences and certain core cooling mode failures are overlapped to meet the requirement [ mode 1, mode 2 and mode 3].
Finally, carrying out human factor verification, determining whether the user requirement is met, and if the user requirement is not met, modifying according to the opinion of the user until the user requirement is met.
(5) Determining core cooling function control strategy
After the final strategy verification is completed, a final core cooling control strategy is formed.
It will be apparent to those skilled in the art that various modifications and variations can be made to the present invention without departing from the spirit or scope of the invention. Thus, it is intended that the present invention also include such modifications and alterations insofar as they come within the scope of the appended claims or the equivalents thereof.
Claims (5)
1. A design method of a nuclear power plant reactor core cooling function control strategy based on symptoms comprises the following steps:
(1) Performing core cooling symptom limit value analysis, determining an instrument combination theta for representing insufficient core cooling, and obtaining the limit value requirement of instrument readings in the core cooling symptom instrument combination theta, wherein the specific method comprises the following steps: the method comprises the steps of establishing a function set of unit safety criterion requirement parameters and meter readings by analyzing the change relation of the unit safety criterion requirement parameters and the meter readings, representing a limiting range in the unit safety criterion according to core cooling key symptoms, and obtaining the limit value requirement of the meter readings in the core cooling characterization symptom meter combination theta according to the corresponding function relation;
(2) Determining a list of incidents in which core cooling is challenged;
(3) The method comprises the steps of analyzing a core cooling mode of a nuclear power plant, determining a core cooling mode set omega, and determining an optimal core cooling mode sequence according to comprehensive cooling capacity sequencing of the core cooling modes, wherein the specific method comprises the following steps: analyzing the cooling capacity of each core cooling mode in the core cooling mode set omega and analyzing the reliability of each core cooling mode through core physical and thermal hydraulic simulation calculation, analyzing the sub-function capacity of each core cooling mode in the core cooling mode set omega and completing quantification, normalizing to be a specific numerical value as a sub-function capacity evaluation number, determining the weight factor of each sub-function based on the safety and economical targets of the nuclear power plant and completing normalization; combining the sub-function capacity evaluation number of each core cooling mode and the corresponding sub-function weight factors, quantitatively determining to obtain the comprehensive cooling capacity of each core cooling mode, and determining the optimal core cooling mode sequence according to the comprehensive cooling capacity sequence of the core cooling modes;
(4) Verifying and adjusting the sequence of the cooling modes of the reactor core determined in the step (3) aiming at the accident conditions in the accident list of which the cooling of the reactor core is challenged determined in the step (2);
(5) A final core cooling function control strategy is determined.
2. The method of designing a symptom-based nuclear power plant core cooling function control strategy of claim 1, wherein: in the step (1), according to design characteristics of a nuclear power plant, core physical and thermal hydraulic simulation calculation and experimental results, core cooling key sign representation is determined, meters for representing the physical quantities are determined through abnormal physical quantities when the core is insufficiently cooled, and then meter combination theta for representing the core is determined.
3. The method of designing a symptom-based nuclear power plant core cooling function control strategy of claim 1, wherein: in the step (2), according to the rule standard and related accident lists concerned and required by the nuclear security department, and in combination with the design of the nuclear power plant, the accident list of the unit which is challenged to the cooling of the reactor core is determined through the security analysis and related simulation calculation of the accidents in all the accident lists, so that the accident condition needing to be subjected to the cooling analysis of the reactor core is determined.
4. The method of designing a symptom-based nuclear power plant core cooling function control strategy of claim 1, wherein: and (3) determining setting value requirements to be met by executing relevant core cooling measures in each core cooling mode through calculation and analysis, so that core cooling based on the core cooling modes can ensure that meter readings in the core cooling characterization sign meter combination theta meet limit value requirements.
5. The method of designing a symptom-based nuclear power plant core cooling function control strategy of claim 1, wherein: in the step (4), the verification and adjustment modes are as follows:
(4-1) verifying whether the single core cooling mode meets the requirement of the meter reading limit value, if not, re-determining the core cooling mode according to the unit design and the core working condition simulation calculation in the step (3);
(4-2) verifying whether the combination of failure of one core cooling mode in the core cooling mode sequence stack meets the requirement of the meter reading limit value, if not, re-designing according to the unit, combining core working condition simulation calculation, and returning to the step (3) to re-determine the core cooling mode;
and (4-3) performing human factor verification, determining whether the human factor meets the requirements of the design criteria, and if not, modifying according to the verification result until the requirements are met.
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