CN115331856A - Method and system suitable for establishing passive nuclear power plant seismic equipment list - Google Patents
Method and system suitable for establishing passive nuclear power plant seismic equipment list Download PDFInfo
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- CN115331856A CN115331856A CN202210899129.5A CN202210899129A CN115331856A CN 115331856 A CN115331856 A CN 115331856A CN 202210899129 A CN202210899129 A CN 202210899129A CN 115331856 A CN115331856 A CN 115331856A
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- 238000000034 method Methods 0.000 title claims abstract description 28
- 238000012216 screening Methods 0.000 claims abstract description 25
- 230000000977 initiatory effect Effects 0.000 claims abstract description 16
- 230000006870 function Effects 0.000 claims description 15
- 238000004590 computer program Methods 0.000 claims description 6
- 238000001816 cooling Methods 0.000 claims description 6
- 239000002826 coolant Substances 0.000 claims description 3
- 230000005611 electricity Effects 0.000 claims description 3
- 238000002955 isolation Methods 0.000 claims description 3
- 239000000126 substance Substances 0.000 claims description 3
- 230000033001 locomotion Effects 0.000 description 7
- 238000004458 analytical method Methods 0.000 description 5
- 238000012502 risk assessment Methods 0.000 description 4
- 230000035939 shock Effects 0.000 description 4
- 230000000116 mitigating effect Effects 0.000 description 3
- 230000008569 process Effects 0.000 description 3
- 230000004044 response Effects 0.000 description 3
- 230000001052 transient effect Effects 0.000 description 3
- 230000000694 effects Effects 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 238000011002 quantification Methods 0.000 description 2
- 238000012300 Sequence Analysis Methods 0.000 description 1
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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
- G21D3/002—Core design; core simulations; core optimisation
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
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Abstract
The invention belongs to the technical field of list establishment, and provides a method and a system suitable for establishing a seismic equipment list of a passive nuclear power plant, wherein the method comprises the steps of screening out equipment which is inherently rigid to an earthquake in a preliminary seismic equipment list to obtain a screened seismic equipment list; and then, screening out the equipment which can not cause the earthquake initiating event and influence the accident relieving function in the screened seismic equipment list to obtain a final seismic equipment list, reasonably controlling the quantity of the seismic equipment through twice screening, and remarkably improving the efficiency of building the seismic equipment list of the passive nuclear power plant and simultaneously ensuring the integrity of the seismic equipment list.
Description
Technical Field
The invention belongs to the technical field of list establishment, and particularly relates to a method and a system suitable for establishing a seismic equipment list of a passive nuclear power plant.
Background
In the earthquake Probability Safety Assessment (PSA), a system response analyst and an earthquake vulnerability Assessment officer jointly develop a preliminary earthquake equipment list (SEL) based on preliminary insights in earthquake risk analysis and the existing internal event PSA model and the earthquake PSA model developed by similar power plants. The list should include all systems and equipment that provide relief from earthquake induced damage conditions, and the building structures associated with them. The list should also allow for mitigation of fire and flooding due to earthquakes. If non-secure systems and devices are deemed relevant to achieving a safe trip, they should also be included in the manifest.
The inventor finds that the existing method suitable for establishing the seismic equipment list of the passive nuclear power plant has the problems of complicated steps, complex screening process and efficiency.
Disclosure of Invention
The invention aims to solve the problems and provides a method and a system suitable for building a seismic equipment list of a passive nuclear power plant, which can obviously improve the building efficiency of the seismic equipment list of the passive nuclear power plant, ensure the integrity of the seismic equipment list and provide more reasonable risk insight for the operation management of the nuclear power plant.
In a first aspect, the invention provides a method for building a list of seismic equipment in a passive nuclear power plant, comprising the following steps:
establishing a preliminary seismic equipment list according to the system specification;
screening out the devices which belong to inherent rigidity to the earthquake in the preliminary earthquake device list to obtain a screened earthquake device list;
and screening out the equipment which can not cause the earthquake initial event and influence the accident relieving function in the screened earthquake equipment list to obtain a final earthquake equipment list.
Furthermore, according to the system specification, the earthquake-resistant I-type equipment of the security system and the earthquake-resistant I-type valve which executes the containment isolation function in the non-security system are selected, and a preliminary earthquake equipment list is obtained.
Further, the safety level system comprises a reactor coolant system, a passive core cooling system and a passive containment cooling system.
Further, non-safety level systems include chemical and volume control systems as well as instrumentation and compressed air systems.
Further, devices that are inherently rigid with respect to earthquakes include check valves, manual valves, and orifice plates; the manual valve comprises a stop valve, a ball valve, a plug valve and a butterfly valve.
Further, non-seismic type I devices in the final seismic equipment list are identified, and whether any relevant devices can cause breach type initiating events, loss of off-plant electricity initiating events and core power increase type initiating events is identified.
And further, selecting the earthquake-resistant plants of the equipment in the earthquake equipment list.
In a second aspect, the present invention further provides a system for building a list of seismic equipment in a passive nuclear power plant, including:
a preliminary seismic device inventory build module configured to: establishing a preliminary seismic equipment list according to the system specification;
a seismic device inventory screening module configured to: screening out the devices which belong to inherent rigidity to the earthquake in the preliminary earthquake device list to obtain a screened earthquake device list;
a final seismic equipment inventory build module configured to: and screening out the equipment which can not cause the earthquake initiating event and influence the accident relieving function in the screened earthquake equipment list to obtain a final earthquake equipment list.
In a third aspect, the present invention further provides an electronic device, including a memory, a processor, and a computer program stored in the memory and executable on the processor, where the processor executes the program to implement the steps of the method for list establishment of seismic equipment in a passive nuclear power plant as described in the first aspect.
In a fourth aspect, the invention also provides a computer-readable storage medium, on which a computer program is stored, which program, when being executed by a processor, carries out the steps of the method for passive nuclear power plant seismic equipment inventory build-up as described in the first aspect.
Compared with the prior art, the invention has the following beneficial effects:
1. the method includes the steps that devices which are inherently rigid to earthquakes in a preliminary earthquake device list are screened out, and a screened earthquake device list is obtained; then, equipment which does not cause earthquake starting events and influence the accident relieving function in the screened seismic equipment list is screened out to obtain a final seismic equipment list, the quantity of the seismic equipment is reasonably controlled through twice screening, the efficiency of building the seismic equipment list of the passive nuclear power plant can be remarkably improved, and meanwhile the integrity of the seismic equipment list is ensured;
2. on the premise of not influencing the calculation accuracy of the follow-up earthquake PSA, the invention reasonably controls the quantity of the earthquake equipment by introducing relevant assumptions suitable for the passive nuclear power plant, and can remarkably improve the efficiency of building the earthquake equipment list of the passive nuclear power plant through layer-by-layer screening of the system and the equipment, ensure the integrity of the earthquake equipment list and provide more reasonable risk insight for the operation management of the nuclear power plant.
Drawings
The accompanying drawings, which form a part hereof, are included to provide a further understanding of the present embodiments, and are incorporated in and constitute a part of this specification, illustrate exemplary embodiments of the present embodiments and together with the description serve to explain the present embodiments without unduly limiting the present embodiments.
FIG. 1 is a flow chart of example 1 of the present invention.
The specific implementation mode is as follows:
the invention is further described with reference to the following figures and examples.
It should be noted that the following detailed description is exemplary and is intended to provide further explanation of the disclosure. Unless defined otherwise, all technical and scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this application belongs.
From the purpose of seismic PSA analysis, the key technical links of seismic PSA can be summarized as seismic hazard analysis, seismic vulnerability assessment, and system response analysis.
The earthquake risk analysis aims to obtain the occurrence frequency of earthquake motions (such as peak ground acceleration, PGA) with different intensities of a plant site and determine the occurrence frequency of earthquake initiating events. Seismic PSA typically selects a single parameter (usually PGA) to represent plant site seismic motion. Similar to other initiating events, the plant seismic damage status (similar to the initiating event of an internal event) that causes the same impact and requires similar mitigation functions should be categorized. The selected earthquake motion parameters represent the influence effect of earthquake events on the power plant, and earthquakes caused by different earthquake magnitudes or different earthquake faults can generate the same earthquake motion at the site. The risk analysis link must consider all types of seismic sources and classify them accordingly when assessing the frequency of occurrence of different levels of seismic activity. And a great deal of uncertainty exists in the process of identifying and grouping the seismic sources, and the seismic sources are tracked. Each seismic risk curve is assigned a weight value at the discretion of the analyst, which represents the analyst's confidence in the likelihood of the occurrence of the actual seismic hazard depicted by the curve. After different earthquake initiating event intervals are defined by using the specific earthquake motion parameters, the earthquake initiating event frequency of the corresponding interval can be obtained by subtracting the overtaking frequencies corresponding to two adjacent earthquake motion parameters on the same curve.
The objective of seismic vulnerability assessment is to assess the conditional probability of failure of vital structures and equipment (i.e., those structures, systems and components that are most essential to plant safety). Earthquake vulnerability can be developed through power plant design information and actual reaction analysis, and on-site patrol is very important in the process. In order to quantify an event sequence, it is necessary to obtain a conditional failure probability corresponding to a specific earthquake motion parameter, that is, a failure probability corresponding to each earthquake-initiated event. For a single SSC of a power plant, several monotonically increasing curves represent its seismic vulnerability, and a family of discrete vulnerability curves represents the uncertainty distribution of a particular failure mode. Similar to the seismic risk analysis, each curve in the family is assigned a weight value representing the degree of certainty that the analyst is. From these curves, the conditional failure probability and uncertainty distribution for a particular SSC for each seismic event interval (seismic interval) can be determined.
The system response analysis link can be divided into two parts of earthquake PSA model establishment and earthquake risk quantification. The earthquake PSA model is used for establishing the condition of reactor core damage caused by the failure of structures and equipment caused by earthquake, including establishing an event tree of event sequence analysis and establishing a logic model for a single event tree header event; while taking into account failures directly caused by earthquakes, random failures and errors in operator action. In order to consider failure modes directly caused by earthquakes in logic, relevant professional judgment needs to be combined. Seismic risk quantification requires integration of a seismic risk curve and a seismic vulnerability curve to quantitatively analyze the occurrence frequency of a seismic event sequence.
Example 1:
as shown in FIG. 1, the invention provides a method for building a list of seismic equipment in a passive nuclear power plant, which comprises the following steps:
establishing a preliminary seismic equipment list according to the system specification;
screening out the devices which belong to inherent rigidity to the earthquake in the preliminary earthquake device list to obtain a screened earthquake device list;
and screening out the equipment which can not cause the earthquake initial event and influence the accident relieving function in the screened earthquake equipment list to obtain a final earthquake equipment list.
Screening out the devices which belong to inherent rigidity to the earthquake in the preliminary earthquake device list to obtain a screened earthquake device list; and then screening out the equipment which can not cause the earthquake initiating event and influence the accident relieving function in the screened list of the seismic equipment to obtain a final list of the seismic equipment, reasonably controlling the quantity of the seismic equipment through twice screening, remarkably improving the efficiency of building the list of the seismic equipment of the passive nuclear power plant, and simultaneously ensuring the integrity of the list of the seismic equipment. The specific steps of this embodiment are:
s1, selecting anti-seismic I-type equipment of a security level system according to a system specification; for a passive nuclear power plant, the safety level system mainly comprises a reactor coolant system, a passive core cooling system, a passive containment cooling system and the like; the system specification can be understood as one or more of a construction specification, an equipment introduction specification or a working specification of the passive nuclear power plant, and the system specification can be understood as including all or part of anti-seismic I-type equipment.
The establishment of the seismic equipment list is based on the equipment list of the system specification and an established primary/secondary probability safety evaluation (PSA) model of the internal event power operation condition; also, consider passive components such as tanks, cabinets, cable trays and warm-air ducts that may be screened out in the internal event model.
S2, selecting the anti-seismic type I valves which execute important functions such as containment isolation and the like in non-safety-level systems (such as a chemical and volume control system, an instrument, a compressed air system and the like) according to the system specification.
Through steps S1 and S2, a preliminary SEL is formed. The preliminary SEL is then screened.
S3, the check valve, the manual valve, the orifice plate and the like generally have high shock resistance and are considered to be Inherently rigid (Inherenty Rugged) for earthquakes, and the manual valve comprises a stop valve, a ball valve, a plug valve and a butterfly valve, so that the check valve, the manual valve, the orifice plate and the like are screened out in the step.
And S4, judging the rest equipment one by one from two aspects of whether earthquake initiating events can be caused by earthquake failure and whether the accident relieving function in the earthquake PSA is influenced or not under the earthquake condition, and screening the rest equipment if the earthquake initiating events cannot be caused and the accident relieving function cannot be influenced.
And forming the screened anti-seismic I-type SEL through the step S3 and the step S4.
S5, identifying non-anti-seismic I-type equipment, and according to the technical scheme, mainly identifying whether related equipment possibly causes breach type initial events, loss of off-plant electricity initial events and core power increase type initial events; transient events caused by other non-ruggedized class I devices are all enveloped by lost off-plant power-initiated events and are not identified in detail in this step.
The accident mitigation function of non-seismic class I devices is not considered, but if failure of these devices in the event of an earthquake results in an earthquake-initiated event, then consideration is given; meanwhile, earthquake initial events caused by non-earthquake-resistant I-type equipment are divided into breach initial events, loss-of-plant-outside-power initial events, core power increase initial events and other transient initial events; since the shock resistance of the device associated with the off-plant power is the lowest among all the non-shock resistant class I devices, the transient events caused for the non-shock resistant class I devices are enveloped by the loss of off-plant power initiated events; the anti-seismic I-type pipeline has stronger anti-seismic performance, and the failure mode of the anti-seismic I-type pipeline breakage caused by the earthquake is not considered.
And S6, selecting the earthquake-resistant factory buildings containing the equipment in the SEL list. And (5) obtaining the final SEL after the steps are completed.
Through the steps, the efficiency of establishing the seismic equipment list of the passive nuclear power plant can be remarkably improved, the integrity of the seismic equipment list is ensured, and more reasonable risk insight is provided for the operation management of the nuclear power plant.
Example 2:
the embodiment provides a system suitable for passive nuclear power plant seismic equipment list building, which comprises:
a preliminary seismic device inventory building module configured to: establishing a preliminary seismic equipment list according to the system specification;
a seismic device inventory screening module configured to: screening out the equipment which belongs to inherent rigidity to the earthquake in the preliminary earthquake equipment list to obtain a screened earthquake equipment list;
a final seismic equipment inventory build module configured to: and screening out the equipment which can not cause the earthquake initial event and influence the accident relieving function in the screened earthquake equipment list to obtain a final earthquake equipment list.
The working method of the system is the same as the method for establishing the seismic equipment list of the passive nuclear power plant in the embodiment 1, and the detailed description is omitted here.
Example 3:
the embodiment provides an electronic device, which comprises a memory, a processor and a computer program stored on the memory and capable of running on the processor, wherein the processor executes the program, and the steps in the method for establishing the passive nuclear power plant seismic equipment list in embodiment 1 are realized.
Example 4:
the present embodiment provides a computer-readable storage medium, on which a computer program is stored, which when executed by a processor, implements the steps of the method for passive nuclear power plant seismic equipment inventory build described in embodiment 1.
The above description is only a preferred embodiment of the present invention, and is not intended to limit the present invention, and those skilled in the art can make various modifications and variations. Any modification, equivalent replacement, or improvement made within the spirit and principle of the present embodiment should be included in the protection scope of the present embodiment.
Claims (10)
1. A method for building a seismic equipment list of a passive nuclear power plant is characterized by comprising the following steps:
establishing a preliminary seismic equipment list according to the system specification;
screening out the equipment which belongs to inherent rigidity to the earthquake in the preliminary earthquake equipment list to obtain a screened earthquake equipment list;
and screening out the equipment which can not cause the earthquake initial event and influence the accident relieving function in the screened earthquake equipment list to obtain a final earthquake equipment list.
2. The method for building the seismic equipment list of the passive nuclear power plant as claimed in claim 1, wherein according to the system specification, the earthquake-resistant class I equipment of the security level system and the earthquake-resistant class I valve in the non-security level system for executing the containment isolation function are selected to obtain a preliminary seismic equipment list.
3. The method for the inventory build of seismic equipment in a passive nuclear power plant of claim 2, wherein the safety level systems include a reactor coolant system, a passive core cooling system, and a passive containment cooling system.
4. The method of claim 2, wherein the non-safety level systems include chemical and volumetric control systems and instrumentation and compressed air systems.
5. The method of claim 1, wherein the devices that are inherently rigid with respect to earthquakes include check valves, manual valves, and orifice plates; the manual valve comprises a stop valve, a ball valve, a plug valve and a butterfly valve.
6. The method for building the seismic equipment list of the passive nuclear power plant as claimed in claim 1, wherein the non-seismic type I equipment in the final seismic equipment list is identified, and whether any relevant equipment may cause breach type initiating events, loss of off-plant electricity initiating events and core power increase type initiating events is identified.
7. The method for building the earthquake equipment list of the passive nuclear power plant as claimed in claim 6, wherein earthquake-resistant plants of the equipment in the earthquake equipment list are selected.
8. A system adapted for inventory build of seismic equipment in a passive nuclear power plant, comprising:
a preliminary seismic device inventory build module configured to: establishing a preliminary seismic equipment list according to the system specification;
a seismic device inventory screening module configured to: screening out the equipment which belongs to inherent rigidity to the earthquake in the preliminary earthquake equipment list to obtain a screened earthquake equipment list;
a final seismic equipment inventory build module configured to: and screening out the equipment which can not cause the earthquake initial event and influence the accident relieving function in the screened earthquake equipment list to obtain a final earthquake equipment list.
9. An electronic device comprising a memory, a processor and a computer program stored on the memory and executable on the processor, the processor implementing the steps of the method for inventory build of passive nuclear power plant seismic equipment as claimed in any one of claims 1 to 7 when executing the program.
10. A computer-readable storage medium, having stored thereon a computer program which, when being executed by a processor, carries out the steps of a method for passive nuclear power plant seismic equipment inventory build as claimed in any one of claims 1 to 7.
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Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104915891A (en) * | 2015-05-25 | 2015-09-16 | 苏州热工研究院有限公司 | Risk assessment method of earthquake and external flooding for nuclear power plant |
| KR101725839B1 (en) * | 2015-12-29 | 2017-04-11 | 한국수력원자력 주식회사 | Risk Communication Information Providing System for Nuclear Power Plants Using PSA results |
| CN113972019A (en) * | 2020-07-23 | 2022-01-25 | 华龙国际核电技术有限公司 | Nuclear power plant accident handling strategy generation method and device and electronic equipment |
| CN114118722A (en) * | 2021-11-08 | 2022-03-01 | 上海核工程研究设计院有限公司 | Method for screening and obtaining superposed initial event combination needing risk quantification |
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- 2022-07-28 CN CN202210899129.5A patent/CN115331856B/en active Active
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104915891A (en) * | 2015-05-25 | 2015-09-16 | 苏州热工研究院有限公司 | Risk assessment method of earthquake and external flooding for nuclear power plant |
| KR101725839B1 (en) * | 2015-12-29 | 2017-04-11 | 한국수력원자력 주식회사 | Risk Communication Information Providing System for Nuclear Power Plants Using PSA results |
| CN113972019A (en) * | 2020-07-23 | 2022-01-25 | 华龙国际核电技术有限公司 | Nuclear power plant accident handling strategy generation method and device and electronic equipment |
| CN114118722A (en) * | 2021-11-08 | 2022-03-01 | 上海核工程研究设计院有限公司 | Method for screening and obtaining superposed initial event combination needing risk quantification |
Non-Patent Citations (3)
| Title |
|---|
| S.T.SPERBECK 等: "How to construct a seismic risk model?", KERNTECHNIK, vol. 78, no. 02, pages 113 - 119 * |
| 杨建峰 等: "地震PSA中地震设备清单的筛选方法研究", 中国核科学技术进展报告, vol. 5, pages 82 - 86 * |
| 王照 等: "压水堆核电厂地震概率安全评价开发方法研究", 核科学与工程, vol. 38, no. 02, pages 246 - 255 * |
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