CN114842994A - Accident diagnosis design method for fast reactor nuclear power plant - Google Patents
Accident diagnosis design method for fast reactor nuclear power plant Download PDFInfo
- Publication number
- CN114842994A CN114842994A CN202210252268.9A CN202210252268A CN114842994A CN 114842994 A CN114842994 A CN 114842994A CN 202210252268 A CN202210252268 A CN 202210252268A CN 114842994 A CN114842994 A CN 114842994A
- Authority
- CN
- China
- Prior art keywords
- accident
- procedure
- information
- entrance
- diagnosis
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/001—Computer implemented control
- G21D3/002—Core design; core simulations; core optimisation
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
-
- 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
Landscapes
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Testing And Monitoring For Control Systems (AREA)
Abstract
The invention provides a fast reactor nuclear power plant accident diagnosis design method, which comprises the following steps: (1) based on the accident procedure file list, eliminating procedure files which are not suitable for being guided and executed by the accident diagnosis strategy to form a procedure list guided and executed by the accident diagnosis strategy; (2) on the basis of the procedure list executed under the guidance of the accident diagnosis strategy, sequencing accident procedures; and forming accident diagnosis strategy entrance symptom information based on the entrance symptom information of the accident regulations according to a screening principle, wherein the entrance symptom information is used as a criterion for judging whether to start executing the accident diagnosis strategy; (3) and making an operation flow of the accident diagnosis strategy according to the sequenced procedure list guided to be executed by the accident diagnosis strategy and the entrance symptom information of the accident diagnosis strategy. The method can be used for guiding the design and optimization of accident diagnosis contents in the accident handling guide rules and the accident regulation files of the fast reactor nuclear power plant, perfecting the accident regulation from the aspects of strategies and measures and effectively improving the operation safety of the fast reactor nuclear power plant.
Description
Technical Field
The invention belongs to the design technology of nuclear power plants, and particularly relates to an accident diagnosis design method of a fast reactor nuclear power plant.
Background
The deep defense is a safety design requirement throughout the design safety rules (HAF) implementation of nuclear power plants. As a third defense line of a depth defense principle, the accident rule plays a vital role in limiting the accident development and ensuring the safety of the reactor. Once an event or accident condition occurs, the nuclear power plant is considered to be in an emergency state, requiring operators to react quickly using accident regulations, correct the condition deviations, and take necessary actions to avoid or mitigate possible consequences.
The fast reactor nuclear power plant system is complex and has many operation parameters. The method comprises the following steps of considering a main process system, a safety system, an auxiliary system and a support system which are required by normal operation, abnormal operation working conditions and accident working conditions, wherein the number of systems of a nuclear power plant reaches thousands; the necessary information needed for incident diagnosis includes, but is not limited to, temperature, flow, pressure, distribution board voltage, associated equipment availability, radioactivity levels, integrated signatures based on process equipment status, etc. Thus, the accident protocol involves a number of systems, equipment, operating parameters of the nuclear power plant, and the various steps of the accident handling strategy are influenced and linked. In order to accurately and quickly respond to the accident handling requirement, a scientific and reasonable design method is needed for analysis, and an accurate and efficient accident diagnosis strategy is determined.
Whether the design of the accident diagnosis strategy is reasonable or not is directly related to the operation safety of a power plant, and the advanced accident diagnosis strategy can quickly and accurately call accident procedures to respond, so that the accident process can be better controlled, the accident result can be relieved, and the safety of a unit can be ensured.
Disclosure of Invention
The invention aims to provide an accident diagnosis design method of a fast reactor nuclear power plant based on design characteristics and requirements of the fast reactor nuclear power plant, so that an accurate and efficient accident diagnosis strategy is determined.
The technical scheme of the invention is as follows: a fast reactor nuclear power plant accident diagnosis design method comprises the following steps:
(1) based on the accident procedure file list, eliminating procedure files which are not suitable for being guided and executed by the accident diagnosis strategy to form a procedure list guided and executed by the accident diagnosis strategy;
(2) on the basis of the procedure list executed under the guidance of the accident diagnosis strategy, sequencing accident procedures; and forming accident diagnosis strategy entrance symptom information based on the entrance symptom information of the accident regulations according to a screening principle, wherein the entrance symptom information is used as a criterion for judging whether to start executing the accident diagnosis strategy;
(3) and making an operation flow of the accident diagnosis strategy according to the ordered procedure list guided to be executed by the accident diagnosis strategy and the entrance symptom information of the accident diagnosis strategy.
Further, according to the method for designing the accident diagnosis of the fast reactor nuclear power plant, in the step (1), the accident procedures which are not applicable to the procedure files executed under the guidance of the accident diagnosis strategy are eliminated as follows:
processing accident regulations of unavailable accident conditions of the main control room;
the accident handling work is not an accident procedure which is mainly executed by an operator in a main control room, and comprises the steps that a diagnosis signal is not mainly the signal of the main control room, the accident handling operation is mainly finished on the spot, and the complete flow of the accident handling is not the accident procedure which is mainly finished by the operator in the main control room;
the accident rule is used for monitoring the state of the unit and monitoring the accident operation.
Further, in the method for diagnosing and designing the accident of the fast reactor nuclear power plant, in the step (2), the method for sequencing accident regulations comprises the following steps:
grouping the accident regulations, and sequentially checking according to the grouping sequence and the sequencing in the group in the accident diagnosis strategy so as to enter the proper accident regulations,
the 1 st set of accident protocols includes: processing accident regulations of accident working conditions causing radioactive release consequences and accident regulations of sodium leakage related accident working conditions, wherein the in-group ordering principle is to determine a sequence according to the emergency degree of the related accident working conditions;
the 2 nd group of accident protocols includes: accident regulations related to power supply accidents, accident regulations related to equipment cooling water accidents and accident regulations related to compressed air accidents are processed, and the in-group ordering principle is that the power supply, the equipment cooling water and the compressed air are in sequence;
the 3 rd group of accident rules are other accident rules, and the in-group ordering principle is to determine the sequence according to the emergency degree of the relevant accident conditions.
Further, in the method for designing the fault diagnosis of the fast reactor nuclear power plant, in the step (2), the screening principle of the fault diagnosis strategy entry symptom information includes:
for each procedure, the logic combination result of the selected entrance symptom information can cover all paths entering the procedure;
for each procedure, simplifying the quantity of the selected entrance symptom information; the simplification method comprises the steps of defining all candidate entrance symptom information as a candidate set, analyzing the correlation among the candidate entrance symptom information in the candidate set, and selecting a subset with the best orthogonality according to the correlation analysis;
the entrance symptom information includes a scram signal.
Further, in the method for designing the accident diagnosis of the fast reactor nuclear power plant, in the step (3), the method for making the operation flow of the accident diagnosis strategy is as follows:
(3-1) determining the composition of an operation flow, including entry information, confirmed shutdown, inspection information and execution information;
(3-2) designing the entrance information, and converting the criterion for starting to execute the accident diagnosis strategy into an executable operation flow form;
(3-3) checking a reactor scram, confirming the operation of the scram;
(3-4) for each procedure, combining the accident diagnosis strategy entrance symptom information according to diagnosis logics to form inspection information corresponding to the procedure, directing all logic 'yes' results of the inspection information to the execution of the procedure to form execution information corresponding to the procedure, combining the inspection information and the execution information of all the procedures according to the sequence of the sequenced accident procedures, and sequentially splicing to form a sequential operation flow.
Further, in the method for designing the accident diagnosis of the fast reactor nuclear power plant, in the step (3), the operation process of the accident diagnosis strategy is optimized, and the method includes:
a. for the check information which appears for many times in the operation flow, merging check points on the operation flow, and reducing the repeated check times of the same information in the operation flow as much as possible;
b. for adjacent procedures, the check information is considered to be combined, and the execution flow is optimized.
The invention has the following beneficial effects:
the invention combines the design characteristics of the fast reactor nuclear power plant and the accident regulation system of the fast reactor nuclear power plant for the first time, provides the accident diagnosis design method and strategy of the fast reactor nuclear power plant, can be used for guiding the design and optimization of the accident diagnosis content in the accident handling guide rule and the accident regulation file of the fast reactor nuclear power plant, can improve the accident regulation from the strategy and measures, and effectively improves the operation safety of the fast reactor nuclear power plant.
The invention provides a hierarchical principle in the accident diagnosis strategy, provides a specific sequence for executing diagnosis and examination on the accident procedures, forms a guidance scheme with reasonable logic, clear sequence, accuracy and high efficiency, and solves the core problem of the accident diagnosis strategy design.
The invention solves the problems of complex and various accident conditions, complex fast reactor nuclear power plant system, multiple operation parameters, large digital signal quantity and various types of a main control room, heavy operation tasks and the like when an accident diagnosis strategy is designed in the fast reactor nuclear power plant. According to the method, the high-efficiency accident procedure man-machine interface can be developed, and the procedure execution efficiency is improved. The designed accident diagnosis strategy can remarkably reduce the workload of operator accident diagnosis, greatly reduce the possibility of human error in the accident diagnosis, reduce misdiagnosis and misoperation, improve the unit treatment measures under the accident working condition and ensure the accuracy and timeliness of accident response.
The invention has good universality, and can provide an applicable accident diagnosis strategy or convert the accident diagnosis strategy into an accident diagnosis rule on the basis of an accident rule file list by combining with design schemes such as a protection system, instrument control and the like of a specific fast reactor power plant.
Drawings
FIG. 1 is a flow chart of the accident diagnosis design method of the fast reactor nuclear power plant of the present invention.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is described in further detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative of the invention and are not intended to limit the invention.
The fast reactor nuclear power plant system is complex and has many operation parameters. The accident handling method relates to a large number of systems and equipment of a nuclear power plant, various operation parameters such as temperature, flow, pressure and comprehensive signals, and all steps of an accident handling strategy are mutually influenced and associated. In order to accurately and quickly respond to the accident handling requirement, a scientific and reasonable design method is needed for analysis, and an accurate and efficient accident diagnosis strategy is determined.
The accident conditions of fast reactor accident rule design and coping are complex and various. In the accident condition range, fast reactor accident regulation design deals with all design basis accidents and part over-design basis accidents; in terms of accident condition types, fast reactor accident regulations are designed to deal with accidents occurring in various systems such as a main container, a primary loop, a secondary loop, a three-loop steam turbine, electricity, compressed air, cooling circulating water and the like; on the accident sign, different accident conditions may trigger accident signs such as emergency shutdown signals of the same type, so that the accident conditions can be accurately determined and corresponding accident regulations can be used after the accident signs are distinguished. Therefore, when the accident condition is responded, a complete accident diagnosis strategy is required to be used as a total entrance of an accident rule file system, the accident condition is accurately and quickly determined based on the accident sign, and a corresponding accident rule is called.
Under the design condition of a digital main control room, signals used as the entrance condition of the accident rule comprise warning and non-warning sign signals, and the number is extremely large and the types are various. If the operation task is directly processed by an operator without depending on a reasonably optimized execution strategy, the accident diagnosis process is time-consuming, and the consequences such as human errors are difficult to overcome. Therefore, in order to perfect the handling measures of the unit under the accident condition and ensure the accuracy and timeliness of the accident response, the accident diagnosis strategy needs to be designed according to a reasonable method.
The fast reactor nuclear power plant has obvious difference from the engineering design of the conventional pressurized water reactor nuclear power plant in the aspects of system design, operation mode, accident handling and other engineering designs. Therefore, the design method of the related accident diagnosis strategy developed based on the pressurized water reactor nuclear power plant is difficult to solve the problems in the design process of the accident diagnosis strategy of the fast reactor nuclear power plant, and the design method of the accident diagnosis strategy suitable for the fast reactor nuclear power plant needs to be developed.
The invention specifically describes a design method for diagnosing accidents of a fast reactor nuclear power plant from the aspects of regulation range, investigation sequence, entry mode, operation flow and the like.
1) Scope of regulations
In list 1: based on the accident procedure file list, procedure files which are not suitable for being executed guided by the accident diagnosis strategy are removed, and therefore the procedure range guided by the accident diagnosis strategy is determined.
Principle 11: accident rule for processing working condition of unavailable accident of master control room
For example, fire, high radioactivity, etc. cause the evacuation of the people in the main control room.
Principle 12: accident procedures in which accident management is not performed by the master control room operator
The method comprises the steps of firstly, diagnosing signals are not mainly signals of a main control room, secondly, accident handling operation is mainly finished on site, and thirdly, the complete process of accident handling is not accident regulations which are mainly finished by the main control room.
For example, accident regulations dealing with fuel operated accident conditions.
Principle 13: accident protocol for monitoring unit state and for monitoring accident operation
For example, the incident diagnostic protocol itself.
Form list 2: "protocol inventory guided by incident diagnosis policy".
2) Order of investigation
On the basis of the list 2, the accident rules are sorted according to the following two-level principle. After the accident occurs, the detection is carried out in sequence according to the sequence in the accident diagnosis strategy, so that a proper accident regulation is entered.
Table 1 orders incident rules according to the following two-level principle
Form list 3: "ranked incident diagnosis policy guided protocol List".
3) Mode of entry
The inlet symptom information of the accident regulation of the fast reactor nuclear power plant is various, for example, the temperature or pressure information of various fluids such as coolant demineralized water in the power plant, the running state information or fault signals of various key devices such as a main pump, the radioactivity level information in various areas of the power plant, the voltage or power supply fault signals of the key devices of the power plant, and the like. The method screens the entrance symptom information which accords with the following principles 31-33 on the basis of the list 2 and on the basis of the entrance symptom information of the accident regulation.
Principle 31: emergency shutdown signal
Principle 32: complete principle
For each procedure, the logic combination result of the selected entry symptom information can cover all the paths entering the procedure.
Principle 33: principles of simplification
And for each procedure, the number of the selected entrance symptom information is reduced. The simplification method comprises the steps of defining all candidate entrance symptom information as a candidate set; analyzing the correlation between the candidate entry symptom information (i.e., analyzing the degree of information coincidence between the candidate entry symptom information) inside the candidate set; according to the correlation analysis, the subset with the best orthogonality is selected (namely, the subset with the highest information mutual exclusion degree among the entrance symptom information is selected).
Together with the scram signal, these pieces of information form list 4: "Accident diagnosis policy entry symptom information".
The criterion for starting to execute the accident diagnosis strategy is as follows; the signals in list 4 can be regarded as variables having two states of yes and no; the defined criterion is the result of the or logic operation of the signals in list 4. I.e. when any of the signals in list 4 is present, the implementation of the accident diagnosis strategy is started.
4) Operation process
And (4) making an operation flow of the accident diagnosis strategy according to the list 3, the list 4 and the 'criterion'. After the accident occurs, the operator executes an accident diagnosis strategy according to the operation flow, checks the related information and enters a corresponding accident rule.
The method for making the operation flow comprises the following steps:
A. the operation process composition
The contents of the operation flow include "entry information", "check shutdown", "check information", and "execution information".
B. Portal information
Converting the criterion for starting to execute the accident diagnosis strategy into an executable operation flow form; the downstream link of the entry information is confirmation shutdown.
C. Confirming shutdown
Operations including checking for a reactor scram, confirming the scram; and confirming downstream links of the shutdown as inspection information and execution information.
D. Examination information and execution information
For a rule, taking out related entry symptom information in the list 4, and combining and forming inspection information corresponding to the rule according to reasonable diagnosis logic;
all the logical 'yes' results of the check information point to the execution of the procedure to form the execution information corresponding to the procedure;
and combining the check information and the execution information of all the procedures according to the sequence of the list 3, and sequentially splicing to form a sequential operation flow.
The operation flow established according to the sequence generally comprises redundant flow links, and can be optimized according to the following method:
a. for the check information which appears for many times in the operation flow, optimization such as merging check points and the like is considered on the operation flow, and the repeated check times of the same information in the operation flow are reduced as much as possible;
b. for adjacent procedures, the check information is considered to be combined, and the execution flow is optimized.
Examples
The following specific examples of the above technical solution are as follows:
(1) scope of regulations
On the basis of list 1, according to principles 11, 12, 13, a procedure file is proposed that does not apply to guidance:
TABLE 2 protocol Range screening
List 2 is formed as follows:
TABLE 3 List 2
| Protocol item |
| Procedure 1 |
| Protocol 4 |
| …… |
| Procedure i |
| …… |
| Procedure n |
(2) Order of investigation
The order list of the protocol was built as follows.
Table 4 orders the incident rules according to the following two-level principle
Form list 3: "ranked incident diagnosis policy guided protocol List".
TABLE 5 List 3
| Protocol item | Execution order |
| Procedure 8 | 1 |
| Protocol 11 | 2 |
| Procedure 1 | 3 |
| Protocol 4 | 4 |
| Protocol 5 | 5 |
| Protocol 6 | 6 |
| Procedure 9 | 7 |
| Protocol 10 | 8 |
| Procedure 7 | 9 |
| Protocol 14 | 10 |
| Protocol 13 | 11 |
| Protocol 12 | 12 |
| Protocol 15 | 13 |
(3) Mode of entry
On the basis of the list 2, accident protocol entry symptom information is screened.
Table 6 accident procedure entry symptom information screening
Providing an emergency shutdown signal list:
TABLE 7 Emergency shutdown Signal List
| Emergency shutdown signal | Content providing method and apparatus |
| Emergency shutdown Signal 1 | … … trigger emergency reactor shutdown |
| …… | …… |
| Emergency shutdown signal i | …… |
| …… | …… |
| Emergency shutdown signal | …… |
Table 6 and Table 7 show Table 4.
Table 8 list 4-incident diagnosis policy entry symptom information
| Entrance symptom information | Source |
| Symptom 1: … … | Protocol 1 |
| And (3) sign 2: … … | Procedure 1 |
| …… | …… |
| Symptom i … … | Emergency shutdown signal j |
| …… | …… |
| Symptom n: … … | Protocol 15 |
The or logical operation result of each signal in the list 4 is used as a criterion for judging whether to start executing the accident diagnosis strategy.
(4) Flow of operation
And splicing the entrance information, the confirmed shutdown, the inspection information and the execution information according to a formulation method of the operation flow, and optimizing according to an optimization method to form an accident diagnosis strategy operation flow.
It will be evident to those skilled in the art that the invention is not limited to the details of the foregoing illustrative embodiments, and that the present invention may be embodied in other specific forms without departing from the spirit or essential attributes thereof. The present embodiments are therefore to be considered in all respects as illustrative and not restrictive, the scope of the invention being indicated by the appended claims rather than by the foregoing description, and all changes which come within the meaning and range of equivalency of the claims are therefore intended to be embraced therein. Any reference sign in a claim should not be construed as limiting the claim concerned.
Furthermore, it should be understood that although the present description refers to embodiments, not every embodiment may contain only a single embodiment, and such description is for clarity only, and those skilled in the art should integrate the description, and the embodiments may be combined as appropriate to form other embodiments understood by those skilled in the art.
Claims (8)
1. A fast reactor nuclear power plant accident diagnosis design method is characterized by comprising the following steps:
(1) based on the accident procedure file list, eliminating procedure files which are not suitable for being guided and executed by the accident diagnosis strategy to form a procedure list guided and executed by the accident diagnosis strategy;
(2) on the basis of the procedure list executed under the guidance of the accident diagnosis strategy, sequencing accident procedures; and forming accident diagnosis strategy entrance symptom information based on the entrance symptom information of the accident regulations according to a screening principle, wherein the entrance symptom information is used as a criterion for judging whether to start executing the accident diagnosis strategy;
(3) and making an operation flow of the accident diagnosis strategy according to the ordered procedure list guided to be executed by the accident diagnosis strategy and the entrance symptom information of the accident diagnosis strategy.
2. The accident diagnosis design method for the fast reactor nuclear power plant according to claim 1, characterized in that in the step (1), the accident regulations which are not applicable to the regulation files executed under the guidance of the accident diagnosis strategy are eliminated as follows:
processing accident regulations of unavailable accident conditions of the main control room;
the accident handling work is not an accident procedure which is mainly executed by an operator in a main control room, and comprises the steps that a diagnosis signal is not mainly the signal of the main control room, the accident handling operation is mainly finished on the spot, and the complete flow of the accident handling is not the accident procedure which is mainly finished by the operator in the main control room;
the accident rule is used for monitoring the state of the unit and monitoring the accident operation.
3. The accident diagnosis design method for fast reactor nuclear power plant according to claim 1, characterized in that in the step (2), the accident procedures are sequenced as follows:
grouping the accident regulations, and sequentially checking according to the grouping sequence and the sequencing in the group in the accident diagnosis strategy so as to enter the proper accident regulations,
group 1 accident protocol includes: processing accident regulations of accident conditions causing radioactive release consequences and accident regulations of sodium leakage related accident conditions, wherein the in-group ordering principle is to determine an order according to the emergency degree of the related accident conditions;
the 2 nd group of accident protocols includes: accident regulations related to power supply accidents, accident regulations related to equipment cooling water accidents and accident regulations related to compressed air accidents are processed, and the in-group ordering principle is that the power supply, the equipment cooling water and the compressed air are in sequence;
the 3 rd group of accident rules are other accident rules, and the in-group ordering principle is to determine the sequence according to the emergency degree of the relevant accident conditions.
4. The fast reactor nuclear power plant accident diagnosis design method of claim 1 or 3, characterized in that in the step (2), the screening principle of the accident diagnosis strategy entry symptom information comprises:
for each procedure, the logic combination result of the selected entrance symptom information can cover all paths entering the procedure;
for each procedure, simplifying the quantity of the selected entrance symptom information;
the entrance symptom information includes a scram signal.
5. The fast reactor nuclear power plant accident diagnosis design method of claim 4, characterized in that the method for simplifying the selected entrance symptom information comprises the following steps: and defining all candidate entrance symptom information as a candidate set, analyzing the correlation among the candidate entrance symptom information in the candidate set, and selecting a subset with the best orthogonality as the entrance symptom information of each procedure according to the correlation analysis.
6. The accident diagnosis design method for a fast reactor nuclear power plant according to claim 1, characterized in that in the step (2), when any one signal of the accident diagnosis strategy entry symptom information appears, the accident diagnosis strategy is started to be executed.
7. The accident diagnosis design method for the fast reactor nuclear power plant according to claim 1, characterized in that in the step (3), the operation flow of the accident diagnosis strategy is formulated as follows:
(3-1) determining the composition of an operation flow, including entry information, shutdown confirmation, check information and execution information;
(3-2) designing the entrance information, and converting the criterion for starting to execute the accident diagnosis strategy into an executable operation flow form;
(3-3) checking a reactor scram, confirming the operation of the scram;
(3-4) for each procedure, combining the accident diagnosis strategy entrance symptom information according to diagnosis logics to form inspection information corresponding to the procedure, directing all logic 'yes' results of the inspection information to the execution of the procedure to form execution information corresponding to the procedure, combining the inspection information and the execution information of all the procedures according to the sequence of the sequenced accident procedures, and sequentially splicing to form a sequential operation flow.
8. The fast reactor nuclear power plant accident diagnosis design method of claim 7, characterized in that in the step (3), the operation flow of the accident diagnosis strategy is optimized, and the method comprises the following steps:
a. for the check information which appears for many times in the operation flow, merging check points on the operation flow, and reducing the repeated check times of the same information in the operation flow as much as possible;
b. for adjacent procedures, the check information is considered to be combined, and the execution flow is optimized.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210252268.9A CN114842994A (en) | 2022-03-15 | 2022-03-15 | Accident diagnosis design method for fast reactor nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210252268.9A CN114842994A (en) | 2022-03-15 | 2022-03-15 | Accident diagnosis design method for fast reactor nuclear power plant |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN114842994A true CN114842994A (en) | 2022-08-02 |
Family
ID=82562295
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202210252268.9A Pending CN114842994A (en) | 2022-03-15 | 2022-03-15 | Accident diagnosis design method for fast reactor nuclear power plant |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN114842994A (en) |
-
2022
- 2022-03-15 CN CN202210252268.9A patent/CN114842994A/en active Pending
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN110428919B (en) | Method for designing reactivity control strategy of pressurized water reactor nuclear power plant based on symptoms | |
| Heo et al. | A framework for evaluating the effects of maintenance-related human errors in nuclear power plants | |
| CN109102913B (en) | Design method of fault diagnosis strategy of pressurized water reactor nuclear power plant | |
| Shen et al. | A methodology for collection and analysis of human error data based on a cognitive model: IDA | |
| CN111128425A (en) | Nuclear power plant safety-related system and equipment periodic test supervision requirement execution method | |
| CN109087721B (en) | Fault diagnosis method for pressurized water reactor nuclear power plant | |
| CN114842994A (en) | Accident diagnosis design method for fast reactor nuclear power plant | |
| CN113421670B (en) | Nuclear power plant accident regulation quantitative analysis method and system | |
| CN111627584B (en) | Nuclear power plant symptom guide function recovery accident guide rule confirmation working condition selection method | |
| Ramuhalli et al. | An updated methodology for enhancing risk monitors with integrated equipment condition assessment | |
| Lew et al. | Computerized operator support system for nuclear power plant hybrid main control room | |
| Petrick et al. | Emergency procedures tracking system for nuclear power plants | |
| CN113837535B (en) | Method for backtracking severe accident process of nuclear power plant | |
| Hugo et al. | Development of a Technical Basis and Guidance for Advanced SMR Function Allocation | |
| CN111627583B (en) | Nuclear power plant symptom guide optimal recovery accident guide rule confirmation working condition selection method | |
| Hirschberg | Experiences from dependent failure analysis in nordic countries | |
| Maturana et al. | Application of Technique for Early Consideration of Human Reliability in the Specification of the Maximum Acceptable Probability of Failure on Demand and the Maximum Spurious Operation Frequency of a Floating Nuclear Power Plant Safety Control System | |
| Collins | Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward for 750–800 C Reactor Outlet Temperature | |
| GONG et al. | REVIEW OF RISK-INFORMED SAFETY DESIGN CONCEPT, METHOD AND APPLICATION | |
| Göring | Description language for the modelling and analysis of temporal change of instrumentation and control system structures | |
| CN113792960A (en) | Event sequence determination and quantitative analysis method in probability safety analysis | |
| Yu et al. | Level 1 Probabilistic Safety Analysis (PSA) of TNPP Units 3 and 4 | |
| Ma et al. | Study on Different Ways for Selecting NPP Design Extension Conditions | |
| Kharchenko et al. | The Technique and the Experience of Expertise of Software for NPP Instrumentation and Control Systems | |
| Ao et al. | The task displays design methodology study for symptoms-oriented emergency operating procedure |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination |