CN111627583B - Nuclear power plant symptom guide optimal recovery accident guide rule confirmation working condition selection method - Google Patents
Nuclear power plant symptom guide optimal recovery accident guide rule confirmation working condition selection method Download PDFInfo
- Publication number
- CN111627583B CN111627583B CN202010361462.1A CN202010361462A CN111627583B CN 111627583 B CN111627583 B CN 111627583B CN 202010361462 A CN202010361462 A CN 202010361462A CN 111627583 B CN111627583 B CN 111627583B
- Authority
- CN
- China
- Prior art keywords
- working condition
- dba
- accident
- nuclear power
- power plant
- 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.)
- Active
Links
- 238000011084 recovery Methods 0.000 title claims abstract description 64
- 238000012790 confirmation Methods 0.000 title claims abstract description 33
- 208000024891 symptom Diseases 0.000 title claims abstract description 32
- 238000010187 selection method Methods 0.000 title claims description 4
- 238000000034 method Methods 0.000 claims abstract description 41
- 238000013461 design Methods 0.000 claims abstract description 31
- 238000012216 screening Methods 0.000 claims abstract description 16
- 238000004458 analytical method Methods 0.000 claims description 18
- 238000004364 calculation method Methods 0.000 claims description 10
- 238000004088 simulation Methods 0.000 claims description 8
- 230000004044 response Effects 0.000 claims description 5
- 230000009897 systematic effect Effects 0.000 abstract description 4
- 238000010200 validation analysis Methods 0.000 description 9
- 238000011161 development Methods 0.000 description 6
- 238000003745 diagnosis Methods 0.000 description 3
- 238000012546 transfer Methods 0.000 description 3
- 230000010485 coping Effects 0.000 description 2
- 238000002347 injection Methods 0.000 description 2
- 239000007924 injection Substances 0.000 description 2
- 230000009469 supplementation Effects 0.000 description 2
- 238000012795 verification Methods 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 241000150786 Athletes Species 0.000 description 1
- 230000002159 abnormal effect Effects 0.000 description 1
- 230000004888 barrier function Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000013486 operation strategy Methods 0.000 description 1
- 239000000243 solution Substances 0.000 description 1
- 239000013589 supplement Substances 0.000 description 1
- 238000012549 training Methods 0.000 description 1
- 238000011269 treatment regimen Methods 0.000 description 1
- 238000011144 upstream manufacturing Methods 0.000 description 1
Classifications
-
- 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
-
- G—PHYSICS
- G06—COMPUTING; CALCULATING OR COUNTING
- G06Q—INFORMATION AND COMMUNICATION TECHNOLOGY [ICT] SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES; SYSTEMS OR METHODS SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES, NOT OTHERWISE PROVIDED FOR
- G06Q10/00—Administration; Management
- G06Q10/06—Resources, workflows, human or project management; Enterprise or organisation planning; Enterprise or organisation modelling
- G06Q10/063—Operations research, analysis or management
- G06Q10/0635—Risk analysis of enterprise or organisation activities
-
- G—PHYSICS
- G06—COMPUTING; CALCULATING OR COUNTING
- G06Q—INFORMATION AND COMMUNICATION TECHNOLOGY [ICT] SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES; SYSTEMS OR METHODS SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES, NOT OTHERWISE PROVIDED FOR
- G06Q50/00—Information and communication technology [ICT] specially adapted for implementation of business processes of specific business sectors, e.g. utilities or tourism
- G06Q50/06—Energy or water supply
-
- 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
- Business, Economics & Management (AREA)
- Engineering & Computer Science (AREA)
- Human Resources & Organizations (AREA)
- Economics (AREA)
- Physics & Mathematics (AREA)
- Strategic Management (AREA)
- General Physics & Mathematics (AREA)
- Entrepreneurship & Innovation (AREA)
- Health & Medical Sciences (AREA)
- Theoretical Computer Science (AREA)
- General Business, Economics & Management (AREA)
- Tourism & Hospitality (AREA)
- Marketing (AREA)
- Public Health (AREA)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Health & Medical Sciences (AREA)
- Water Supply & Treatment (AREA)
- Emergency Management (AREA)
- Primary Health Care (AREA)
- Development Economics (AREA)
- Game Theory and Decision Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Educational Administration (AREA)
- Operations Research (AREA)
- Quality & Reliability (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention belongs to the field of design of accident operation guidelines of nuclear power plants, and particularly relates to a method for selecting a nuclear power plant symptom-oriented optimal recovery accident guideline confirmation working condition, which comprises the following steps: step S1, screening to obtain a first working condition list containing a first DBA working condition with the greatest security challenge for a nuclear power plant unit; step S2, determining a first best recovery guide according to the first working condition list; step S3, a second working condition list containing second DBA working conditions is obtained according to a second optimal recovery guide rule; and S4, combining the first working condition list and the second working condition list to obtain an optimal recovery guide rule confirmation working condition list. The method solves the technical problem that the screening principle is difficult to establish in the process of confirming the working condition screening work for the symptom-oriented EOP optimal recovery guideline, and makes the establishment of the complete and systematic confirmation work of the optimal recovery accident handling guideline possible.
Description
Technical Field
The invention belongs to the field of design of accident operation guidelines of nuclear power plants, and particularly relates to a method for selecting a condition for confirming an optimal recovery accident guideline of a nuclear power plant symptom guide.
Background
The nuclear power plant accident operation guideline (EOP guideline) is an upstream guiding file of an accident handling procedure (EOP), describes a strategy of accident handling of the nuclear power plant and input information required for compiling the accident handling procedure, and is an important design file of safety in the field of operation of the nuclear power plant.
At present, accident handling strategies adopted in the running process of a nuclear power plant are mainly divided into three types of event guiding, state guiding and symptom guiding according to different diagnosis strategies. The symptom-oriented accident handling strategy mainly determines the operation strategy to be adopted by taking key safety-related parameters as symptoms. The strategy can effectively treat complex working conditions and superposition accidents, has better reading and understanding, and is one of the current internationally advanced nuclear power plant accident treatment strategies.
The development process of the EOP guideline comprises the steps of guideline development, verification, confirmation and the like.
In the prior art, event-oriented accident handling strategies are adopted in nuclear power projects in China, the EOP guideline obtained by the method has definite pertinence to the corresponding accident working conditions, and the accident working conditions corresponding to the guideline are directly selected in the process of selecting the guideline confirmation working conditions. For the first-stage Qinmountain and the third-door No. 1&2 units which also adopt the symptom-oriented accident handling strategy, the selection of the first-stage Qinmountain guidance and confirmation working conditions is obtained according to the past engineering experience, and the content of the first-stage Qinmountain and third-door No. 1&2 unit guidance and confirmation working condition selection is not contained in the technical transfer content, so that a complete and systematic method for selecting the best recovery type accident handling guidance working conditions is not provided in China.
Disclosure of Invention
The third generation nuclear power unit independently developed in China adopts a symptom guiding strategy to develop accident operation guidelines and accident handling rules. The symptom-oriented accident handling regulations consider that the operational safety level of a nuclear power plant is characterized by some safety-related critical parameters, and that changes in these values are referred to as "symptoms" and ensure the integrity of the plant safety barrier as long as the safety-related parameters are within limits. If one or more parameters exceed the safety limits, the nuclear power plant is in an abnormal condition or emergency condition, at which time the operator needs to restore the nuclear power plant to a safe condition using the established accident protocol for the symptoms without first completing a diagnosis regarding the cause and nature of the accident. From a design perspective, the symptom-oriented incident handling guidelines not only consider the handling of design-basis incidents, but also multiple faults. Wherein, the best recovery guide is mainly aimed at the design basic accident condition (DBA condition).
The development process of the symptom-oriented EOP guideline comprises the steps of guideline development, verification, confirmation and the like. In order to ensure the integrity of the diagnosis function of the accident handling strategy and effectively reduce the unbearable confirmation workload in the engineering implementation process, one important task in the guide rule confirmation process is to develop 'confirmation condition screening'.
After completing the preliminary design of the nuclear power plant symptom-oriented EOP guideline, from the point of view closer to the actual operation response of the nuclear power plant, the objective of enabling the initial determination of the power plant design and the guideline design is further confirmed by executing the relevant symptom-oriented EOP guideline, namely:
-the validation symptom-oriented EOP guidance system is capable of diagnosing all incidents in the range of conditions determined at the beginning of the design completely and correctly;
the validation symptom guide EOP guide can successfully handle and mitigate the corresponding accident and bring the power plant into a safe state.
According to the above objective of validation work, to ensure the integrity of the guideline coverage, it is necessary to ensure diagnosability of all incidents in the symptom-oriented EOP originating event list. For the best recovery guideline, the design of the inlet condition has better diagnosability for accident conditions in the DBA working condition list because of better correspondence between the design of the inlet condition and the DBA working condition. Thus, the primary purpose of the best recovery guideline validation is to ensure that the guideline can successfully handle the DBA incident and bring the plant into a safe state.
However, due to regulations and design considerations, there are often a large number of DBAs in the unit design, which can result in little affordable effort if one-by-one analysis validation is performed using a computing platform based on the best estimation procedure. How to select the best recovery guide confirmation working condition through systematic, comprehensive and perfect analysis, effectively identify DBAs with larger threat to the operation safety of the nuclear power plant, and the DBAs become the problems to be solved by the invention.
The invention aims to provide a nuclear power plant symptom guide optimal recovery accident guide rule confirmation working condition selection method based on an optimal estimation thermal hydraulic calculation program. The method has good standardability and universality, and can effectively develop the work of selecting the confirmed working condition based on the sign guide EOP optimal recovery guide of various nuclear power plant designs.
In order to achieve the above purpose, the technical scheme adopted by the invention is a method for selecting the best recovery accident guidance confirming working condition of the nuclear power plant symptom guidance, which is used for selecting the best recovery guidance confirming working condition corresponding to the DBA working condition of the nuclear power plant unit, and comprises the following steps:
step S1, screening the DBA working conditions to obtain a first working condition list comprising a first DBA working condition, wherein the first DBA working condition refers to the DBA working condition with the greatest security challenge for a nuclear power plant unit;
step S2, confirming the first DBA working condition contained in the first working condition list, and determining a first best recovery guide; the first best restoration guideline is the best restoration guideline related to the first DBA working condition;
step S3, confirming a second best recovery guide rule, and obtaining a second working condition list containing second DBA working conditions; the second best recovery guide rule refers to the best recovery guide rule which is not related to the first DBA working condition, and the second DBA working condition refers to the DBA working condition which is related to the second best recovery guide rule, is most severe to the second best recovery guide rule according to the response working condition considered at the beginning of the guide rule design, and is judged and determined by combining engineering experience;
and S4, merging the first working condition list and the second working condition list to obtain an optimal recovery guide rule confirmation working condition list.
Further, in the step S1, the first DBA condition may be screened according to the following criteria:
criterion 1, after an accident, reserving DBA working conditions which cannot completely depend on the self instrument control of a nuclear power plant unit and the automatic action of a process system to limit the accident result within the acceptance criterion requirement of safety analysis;
the technical method adopted when the criterion is used is as follows: using a confirmation tool of the optimal estimated thermodynamic and hydraulic calculation program to carry out simulation calculation on a given original accident, and screening out the calculated corresponding DBA working condition under the condition that any intervention action of an operator is not considered and the corresponding acceptance criterion in accident analysis is not broken through;
criterion 2, in the design of a nuclear power plant unit, reserving DBA working conditions which can be dealt with only by adopting innovative safety-related design;
the technical method adopted when the criterion is used is as follows: a confirmation tool of the optimal estimated thermodynamic and hydraulic calculation program is used for carrying out simulation calculation on an original accident, and the DBA working condition is required to be kept in the first working condition list under the condition that the corresponding acceptance criterion in accident analysis is not broken through the automatic action of a sensitive safety system under the condition that any intervention action of an operator is not considered.
Further, in the step S2, the step of confirming the first DBA working condition included in the first working condition list means that the first DBA working condition is simulated by using a thermodynamic and hydraulic calculation program based on the best estimation as a confirming tool, and the confirming operation is performed by using the first best recovery guide corresponding to the first DBA working condition.
Further, the step S3 is repeatedly performed until all the second best restoration guides are confirmed.
The invention has the beneficial effects that:
1. the method solves the technical problem that the screening principle is difficult to establish in the process of confirming the working condition screening work for the symptom-oriented EOP optimal recovery guideline, and makes the establishment of the complete and systematic confirmation work of the optimal recovery accident handling guideline possible.
2. The method provided by the invention can balance the coverage area of the optimal recovery guide confirmation work and the effective control workload, thereby ensuring the integrity of the optimal recovery guide confirmation working condition list and improving the efficiency of the confirmation work.
3. By the method provided by the invention, the safety and completeness of the design of the nuclear power plant can be determined by analyzing the working condition list through the determined optimal recovery guide rule, and the relatively weak links of the design can be found, so that the safety and economy of the nuclear power plant are improved.
4. The method provided by the invention can provide the range of the condition of confirming the symptom-oriented EOP optimal recovery guideline, and the condition can provide basis for the training and other works of operators in newly built nuclear power plants.
Drawings
FIG. 1 is a flow chart of a method for selecting a nuclear power plant symptom oriented optimal recovery accident guideline confirmation condition according to an embodiment of the present invention.
Detailed Description
The invention is further described below with reference to the drawings and examples.
As shown in fig. 1, the method for selecting the best recovery guide rule of the nuclear power plant symptom guide and the best recovery accident guide provided by the invention is used for selecting the best recovery guide rule corresponding to the DBA working condition of the nuclear power plant unit, and comprises the following steps:
step S1, DBA working condition screening, which comprises the following steps:
preliminary screening is carried out on DBA working conditions to obtain a first working condition list comprising first DBA working conditions, wherein the first DBA working conditions refer to DBA working conditions with the greatest security challenges for a nuclear power plant unit;
the first DBA operating condition may be filtered according to the following criteria:
criterion 1, reserving DBA working conditions corresponding to accidents which cannot be relieved by automatic actions; after an accident occurs, the DBA working conditions which cannot completely depend on the self instrument control of the nuclear power plant unit and the automatic action of a process system to limit the accident result within the acceptance criterion requirement of safety analysis are reserved;
the technical method adopted when the criterion is used is as follows: using a confirmation tool of the optimal estimated thermodynamic and hydraulic calculation program to carry out simulation calculation on a given original accident, and screening out the calculated corresponding DBA working condition under the condition that any intervention action of an operator is not considered and the corresponding acceptance criterion in accident analysis is not broken through; the optimal estimation thermodynamic and hydraulic calculation program is usually used as a main tool for accident safety analysis, and the safety analysis program is gradually developed from a conservative and extensive evaluation model program (EM) to a truly fine optimal estimation program (BE) along with the continuous understanding of the thermodynamic and hydraulic phenomenon of a reactor and the development of computer technology in the later period; among the best known estimated thermodynamic and hydraulic calculation programs include RELAP5 (U.S.), TRAC (U.S.), ATHLET (Germany), CATHARE (France), etc.;
criterion 2, reserving DBA working conditions corresponding to related accidents of the innovative design; namely, in the design of the nuclear power plant unit, the DBA working condition which can be dealt with only by adopting innovative safety-related design is reserved;
the technical method adopted when the criterion is used is as follows: the method comprises the steps that a confirmation tool of an optimal estimation thermodynamic hydraulic calculation program is used for carrying out simulation calculation on an original accident, and under the condition that any intervention action of an operator is not considered, if a corresponding acceptance criterion in accident analysis is required to be automatically acted through a sensitive safety system, the DBA working condition is required to be kept in a first working condition list; the sensitive safety system is an innovative system which needs to pay additional attention in the design of the nuclear power plant according to engineering judgment;
step S2, computing a confirmation, comprising:
confirming a first DBA working condition contained in a first working condition list, and determining a first best recovery guide rule; the first best recovery guide is the best recovery guide related to the first DBA working condition;
the step of confirming the first DBA working condition contained in the first working condition list is that a thermodynamic and hydraulic calculation program based on the best estimation is used as a confirming tool, the first DBA working condition is simulated and calculated, and a first best recovery guide rule corresponding to the first DBA working condition is used for carrying out confirming work;
step S3, the guideline confirms the integrity analysis (including working condition supplementation), and determines a supplementation working condition list required for confirming the integrity based on the best restoration guideline
Comprising:
confirming and analyzing a second best recovery guide rule to obtain a second working condition list (a supplementary working condition list) containing second DBA working conditions; the second best recovery guide rule refers to the best recovery guide rule which is not related to the first DBA working condition, and the second DBA working condition refers to the DBA working condition which is related to the second best recovery guide rule, is based on the response working condition considered at the beginning of the guide rule design, and is required to be supplemented into the first working condition list after being analyzed by combining engineering experience judgment and decision theory; the second DBA regime is the most severe DBA regime for the second best recovery guideline; on the basis of confirming the first optimal restoration guidance related to the first DBA working condition, checking the integrity condition of all the optimal restoration guidance confirming ranges, confirming the optimal restoration guidance not related to the first DBA working condition, and according to the response event considered at the beginning of the design of the second optimal restoration guidance, combining engineering experience judgment and decision analysis to obtain a supplementary working condition list; that is, for the best recovery guidelines which are not yet confirmed, according to the coping events considered at the beginning of the design of the guidelines, combining engineering experience judgment and definitive analysis to supplement part of working conditions;
repeatedly executing the step S3 until all second best restoration guides are confirmed, and finally obtaining a complete second working condition list (supplementary working condition list);
and S4, combining the first working condition list and the second working condition list to obtain a complete optimal recovery guide rule confirmation working condition list.
Finally, the practical application of the method for selecting the working condition is demonstrated by illustrating the method for selecting the optimum recovery accident guidance of the nuclear power plant symptom guidance.
1) And (3) according to the DBA working condition list of the nuclear power plant, adopting an analysis method based on a conservative assumption to perform preliminary screening, and searching the DBA working condition with the greatest challenge to the safety of the unit. The specific method comprises the following steps: using a confirmation tool of the optimal estimation thermodynamic hydraulic calculation program to carry out simulation calculation, and screening out calculated corresponding DBA working conditions under the condition that any intervention action of operators is not considered, if the corresponding acceptance criterion in accident analysis is not broken through; the DBA operating conditions addressed with the safety-related innovative design are preserved. The DBA working condition list obtained after screening based on the method is as follows:
| sequence number | Event(s) |
| 1 | Water supply system pipe break |
| 2 | Steam generator heat transfer tube breakage |
| 3 | Minor duct rupture on primary side outside containment |
| … | … |
2) From the aspect of the integrity of the best recovery guide validation work, based on the screened DBA working condition list, using a thermodynamic and hydraulic calculation program based on best estimation as a validation tool, performing simulation calculation on all working conditions in the working condition list, and performing validation work by using related guides, and determining the coverage condition of the working conditions on the best recovery guide according to the validation result, wherein the result is shown in the following table:
3) The optimal recovery guideline which is not covered is analyzed according to the coping working condition considered at the beginning of the guideline design and combining engineering experience judgment and certainty theory to obtain the following supplementary working condition list:
after analysis, it is ensured that all the best estimation directives are confirmed, this step is completed.
4) And 2) integrating the screened DBA working condition list and the supplementary working condition list obtained in the steps 1) and 3) to obtain an optimal recovery guide confirming working condition list, wherein the list is as follows:
| sequence number | Event(s) |
| 1 | Water supply system pipe break |
| 2 | Steam generator heat transfer tube breakage |
| 3 | Minor duct rupture on primary side outside containment |
| 4 | Major breach of primary circuit + failure of all safety injection/low pressure safety injection systems |
| 5 | The atmospheric discharge valves of the three steam generators are blocked and opened |
| 6 | Loss of full ac power |
| … | … |
And then, according to the list, expanding the confirming working condition calculation work based on the symptom of the best estimated thermodynamic hydraulic calculation program and leading to the EOP best recovery guide, and executing the operation applicability confirmation of the operator. And modifying the symptom-oriented EOP optimal restoration guidelines according to the confirmation results, wherein the symptom-oriented EOP optimal restoration guidelines are used for guiding the development of the symptom-oriented EOP optimal restoration procedures used in the follow-up nuclear power plant main control room.
The device according to the invention is not limited to the examples described in the specific embodiments, and a person skilled in the art obtains other embodiments according to the technical solution of the invention, which also belong to the technical innovation scope of the invention.
Claims (3)
1. A nuclear power plant symptom-oriented optimal recovery accident guidance confirming working condition selection method is used for selecting the confirming working condition of the optimal recovery guidance corresponding to the DBA working condition of a nuclear power plant unit, and comprises the following steps:
step S1, screening the DBA working conditions to obtain a first working condition list comprising a first DBA working condition, wherein the first DBA working condition refers to the DBA working condition with the greatest security challenge for a nuclear power plant unit;
step S2, confirming the first DBA working condition contained in the first working condition list, and determining a first best recovery guide; the first best restoration guideline is the best restoration guideline related to the first DBA working condition;
step S3, confirming a second best recovery guide rule, and obtaining a second working condition list containing second DBA working conditions; the second best recovery guide rule refers to the best recovery guide rule which is not related to the first DBA working condition, and the second DBA working condition refers to the DBA working condition which is related to the second best recovery guide rule, is most severe to the second best recovery guide rule according to the response working condition considered at the beginning of the guide rule design, and is judged and determined by combining engineering experience;
s4, merging the first working condition list and the second working condition list to obtain an optimal recovery guide rule confirmation working condition list;
in the step S1, the first DBA working condition is screened according to the following criteria:
criterion 1, after an accident, reserving DBA working conditions which cannot completely depend on the self instrument control of a nuclear power plant unit and the automatic action of a process system to limit the accident result within the acceptance criterion requirement of safety analysis;
the technical method adopted when the criterion is used is as follows: using a confirmation tool of the optimal estimated thermodynamic and hydraulic calculation program to carry out simulation calculation on a given original accident, and screening out the calculated corresponding DBA working condition under the condition that any intervention action of an operator is not considered and the corresponding acceptance criterion in accident analysis is not broken through;
criterion 2, in the design of a nuclear power plant unit, reserving DBA working conditions which can be dealt with only by adopting innovative safety-related design;
the technical method adopted when the criterion is used is as follows: a confirmation tool of the optimal estimated thermodynamic and hydraulic calculation program is used for carrying out simulation calculation on an original accident, and the DBA working condition is required to be kept in the first working condition list under the condition that the corresponding acceptance criterion in accident analysis is not broken through the automatic action of a sensitive safety system under the condition that any intervention action of an operator is not considered.
2. The method as claimed in claim 1, wherein: in the step S2, the step of confirming the first DBA working condition included in the first working condition list means that the first DBA working condition is simulated and calculated by using a thermodynamic and hydraulic calculation program based on the best estimation as a confirming tool, and the confirming work is performed by using the first best recovery guide corresponding to the first DBA working condition.
3. The method as claimed in claim 1, wherein: and repeatedly executing the step S3 until all the second best recovery guide rules are confirmed.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010361462.1A CN111627583B (en) | 2020-04-30 | 2020-04-30 | Nuclear power plant symptom guide optimal recovery accident guide rule confirmation working condition selection method |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010361462.1A CN111627583B (en) | 2020-04-30 | 2020-04-30 | Nuclear power plant symptom guide optimal recovery accident guide rule confirmation working condition selection method |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN111627583A CN111627583A (en) | 2020-09-04 |
| CN111627583B true CN111627583B (en) | 2023-12-26 |
Family
ID=72273206
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202010361462.1A Active CN111627583B (en) | 2020-04-30 | 2020-04-30 | Nuclear power plant symptom guide optimal recovery accident guide rule confirmation working condition selection method |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN111627583B (en) |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR100840858B1 (en) * | 2006-12-20 | 2008-06-23 | 한국전력공사 | Method of developing optimum restoration guideline for steam generator tube leak |
| CN108470592A (en) * | 2018-02-28 | 2018-08-31 | 中国核电工程有限公司 | Expansion application method after a kind of nuclear power plant system accident |
| CN110175811A (en) * | 2019-04-23 | 2019-08-27 | 中国核电工程有限公司 | A kind of functional rehabilitation directive/guide confirmation method based on the best-estimated system program |
| CN110175744A (en) * | 2019-04-23 | 2019-08-27 | 中国核电工程有限公司 | A kind of data processing method of nuclear power plant's accident treatment directive/guide confirmation |
| CN110993135A (en) * | 2019-10-09 | 2020-04-10 | 中国核电工程有限公司 | Sign-based design method for secondary side heat trap control strategy of pressurized water reactor nuclear power plant |
-
2020
- 2020-04-30 CN CN202010361462.1A patent/CN111627583B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR100840858B1 (en) * | 2006-12-20 | 2008-06-23 | 한국전력공사 | Method of developing optimum restoration guideline for steam generator tube leak |
| CN108470592A (en) * | 2018-02-28 | 2018-08-31 | 中国核电工程有限公司 | Expansion application method after a kind of nuclear power plant system accident |
| CN110175811A (en) * | 2019-04-23 | 2019-08-27 | 中国核电工程有限公司 | A kind of functional rehabilitation directive/guide confirmation method based on the best-estimated system program |
| CN110175744A (en) * | 2019-04-23 | 2019-08-27 | 中国核电工程有限公司 | A kind of data processing method of nuclear power plant's accident treatment directive/guide confirmation |
| CN110993135A (en) * | 2019-10-09 | 2020-04-10 | 中国核电工程有限公司 | Sign-based design method for secondary side heat trap control strategy of pressurized water reactor nuclear power plant |
Non-Patent Citations (2)
| Title |
|---|
| 华龙一号设计扩展工况(DEC)选取原则和确定方法;胡凌生;卢放;陶俊;万砺珂;汪景新;陈石;赵鑫樾;谢小龙;;核科学与工程(02);第133-138页 * |
| 核电厂应急运行规程（EOP）技术导则研究;浦胜娣，李吉根，孙礼亚，李运文，林艺，熊平广;中国原子能科学研究院年报(00);第161-162页 * |
Also Published As
| Publication number | Publication date |
|---|---|
| CN111627583A (en) | 2020-09-04 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN109102913B (en) | Design method of fault diagnosis strategy of pressurized water reactor nuclear power plant | |
| CN107767025B (en) | Risk-guided analysis method for loss of coolant accident of large break of nuclear power plant | |
| CN104240781B (en) | Signal distribution method and signal distribution system of digital instrument control system (DCS) of nuclear power plant | |
| CN110428919B (en) | Method for designing reactivity control strategy of pressurized water reactor nuclear power plant based on symptoms | |
| CN108665185A (en) | A kind of design method of nuclear power plant's malfunction protocol scope of application | |
| CN109659053B (en) | Task analysis method for operation strategy development | |
| CN111627583B (en) | Nuclear power plant symptom guide optimal recovery accident guide rule confirmation working condition selection method | |
| CN114923287A (en) | High-pressure heater fault early warning method, system and medium | |
| CN106683727B (en) | Fault monitoring method in accident processing | |
| Papakonstantinou et al. | A simulation based approach to automate event tree generation for early complex system designs | |
| CN109087721B (en) | Fault diagnosis method for pressurized water reactor nuclear power plant | |
| CN111627584B (en) | Nuclear power plant symptom guide function recovery accident guide rule confirmation working condition selection method | |
| CN113421670B (en) | Nuclear power plant accident regulation quantitative analysis method and system | |
| Takizawa et al. | An intelligent man-machine system for future nuclear power plants | |
| CN104966158B (en) | Screening method for influencing time-sensitive accidents without intervention of operators | |
| CN110175744B (en) | Nuclear power plant accident handling guide rule confirmation data processing method | |
| Pavlova et al. | Systematic approach for the analytical validation of Kozloduy NPP, VVER-1000/V320 symptom based emergency operating procedures | |
| CN113837535B (en) | Method for backtracking severe accident process of nuclear power plant | |
| JPS62285172A (en) | On-line fast reasoning method | |
| CN111738557A (en) | Water supply control strategy design method for symptom oriented accident treatment of nuclear power plant | |
| Bae et al. | Predictive fault detection and diagnosis of nuclear power plant using the two-step neural network models | |
| CN111612218B (en) | Method for optimizing symptom-oriented accident guidance operation strategy | |
| CN114694867A (en) | Accident handling system of fast reactor nuclear power plant and design method thereof | |
| CN110943448B (en) | Security control device refusing action fault simulation method, system and storage medium | |
| Laumann et al. | A study on how time pressure and information load affects operators performance in accident scenarios |
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 | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |