A method for evaluating the risk of flooding caused by the rupture of high-energy pipelines in a nuclear power plant and a calculation device

Abstract

A method for evaluating the risk of flooding caused by the rupture of high-energy pipelines in a nuclear power plant, comprising the following steps: providing the initial information of high-energy pipelines and target SSCs in the nuclear power plant, determining the impact of the secondary event effects caused by the rupture of different high-energy pipelines on the target SSCs, and further determining the initiating events caused by the rupture of different high-energy pipelines, establishing an internal flooding probability safety assessment model for the nuclear power plant, substituting the primary event and secondary event of the high-energy pipeline rupture as initial conditions, and calculating the core damage frequency according to the event frequency. This method improves the accuracy of the probabilistic safety assessment of the nuclear power plant by evaluating the secondary events caused by the rupture of high-energy pipelines. The present invention also provides a computing device.

Description

Technical Field

[0001] The present invention belongs to the field of nuclear power, and particularly relates to a method and a computing device for evaluating the risk of flooding caused by the rupture of high-energy pipelines in a nuclear power plant. Background Art

[0002] There are a large number of high-energy pipelines in nuclear power equipment. These pipelines are part of a high-energy system or have a relatively high temperature or pressure inside themselves under normal operating conditions. Once an accident occurs, the risk of rupture of high-energy pipelines becomes one of the inducements for internal flooding accidents in nuclear power plants. At present, the conventional method for calculating the internal flooding risk of nuclear power plants adopts the Guidelines for Performance of Internal Flooding Probabilistic Risk Assessment recommended by the Electric Power Research Institute (EPRI) of the United States. This method can only evaluate ordinary flooding accidents, and the hazards of secondary effects such as pipe whip, jet impact, and compartment pressurization caused by the rupture of high-energy pipelines are not reflected. This leads to a deviation between the current simulation calculation of the internal flooding risk of nuclear power plants and the engineering reality, posing a potential hazard to the accuracy of the safety assessment of nuclear power plants. Therefore, providing a method for evaluating the risk of flooding caused by the rupture of high-energy pipelines in a nuclear power plant has positive significance for improving the safety management level of nuclear power plants. Summary of the Invention

[0003] The purpose of the present invention is to provide a method for evaluating the risk of flooding caused by the rupture of high-energy pipelines in a nuclear power plant, so as to improve the accuracy of calculating the probability of flooding accidents in nuclear power plants. The present invention also provides a computing device.

[0004] According to an embodiment of one aspect of the present invention, there is provided a method for evaluating the risk of flooding caused by the rupture of high-energy pipelines in a nuclear power plant. The method includes the following steps: providing initial information of all high-energy pipelines in the nuclear power plant, where the initial information includes spatial distribution information, pipeline pressure, pipeline length, flow rate, and protection conditions; providing the location information and environmental tolerance information of the target SSC in the nuclear power plant, where SSC refers to structures, systems, and components; analyzing the influence effects of the rupture of each high-energy pipeline and the influence of the influence effects on the target SSC according to the initial information; determining the initiating events caused by the rupture of different high-energy pipelines according to the influence of the influence effects on the target SSC; establishing an internal flooding probabilistic safety assessment model for the nuclear power plant, substituting the initiating events caused by the rupture of different high-energy pipelines into the internal flooding probabilistic safety assessment model for the nuclear power plant, and providing the frequency of each initiating event, and calculating the core damage frequency caused by the flooding accident due to the rupture of high-energy pipelines.

[0005] This method can incorporate secondary events caused by high-energy pipe ruptures into probabilistic safety assessments, overcoming the deficiencies of conventional probabilistic safety assessment methods in comprehensively and conservatively evaluating the consequences of high-energy pipe ruptures, thereby improving the safety management level of nuclear power plants.

[0006] Further, in some embodiments, the influencing effects include one or a combination of pipe whip impact effect, jet impact effect, fluid depressurization transient effect, compartment pressurization effect, environmental condition deterioration effect, and flooding effect.

[0007] Further, in some embodiments, the whip impact effect includes associated pipe ruptures caused by the whip of the high-energy pipe rupture, and the associated pipes include pipes within the whip range of the high-energy pipe without anti-whip components; wherein, the associated pipe ruptures include circumferential / longitudinal pipe ruptures and through cracks, the circumferential / longitudinal pipe ruptures occur in the associated pipes with a smaller pipe diameter than the high-energy pipe where the rupture occurs, and the through cracks occur in the associated pipes with a pipe diameter not less than the high-energy pipe where the rupture occurs.

[0008] Further, in some embodiments, the break flow area of the circumferential / longitudinal pipe rupture is πD1 2 / 4, where D1 is the inner diameter of the pipe; the break flow area of the through crack is D1T / 4, where D1 is the inner diameter of the pipe and T is the wall thickness of the pipe.

[0009] Further, in some embodiments, the evaluation method for the jet impact effect is: based on the initial information of the high-energy pipe, determine the spatial distribution of the jet flow generated when the high-energy pipe has a break, and the target SSC satisfying d≤10D is determined to be failed, and the target SSC satisfying d>10D is determined to be not failed, where d is the distance between the target SSC within the spatial distribution of the jet flow and the break of the high-energy pipe, and D is the diameter of the high-energy pipe.

[0010] Further, in some embodiments, the evaluation methods for the compartment pressurization effect and the environmental condition deterioration effect are: based on the initial information of the high-energy pipe, determine the pressure and environmental condition changes in the compartment where the high-energy pipe is located when the high-energy pipe has a break, and determine whether the target SSC fails according to the environmental tolerance information of the target SSC in the compartment where the high-energy pipe is located, and the environmental conditions include one or a combination of temperature, humidity, nuclear radiation, etc.

[0011] Further, in some embodiments, in the evaluation of the flooding effect, the break flow rate W of the high-energy pipe rupture is 2C D A BR G C, where W is the mass flow rate, C D is the discharge coefficient, A BR is the break area, G C is the critical mass flow velocity; the volumetric flow rate Q of the intermediate-energy pipe rupture I = A c (2ΔPg / Kρ) 0.5 , where Q I is the volumetric flow rate, A c = D I T / 4, T is the wall thickness, D I is the inner diameter of the pipe, g is a given calculation coefficient, ΔP is the pressure difference inside and outside the pipe, K is the loss coefficient, and ρ is the fluid density inside the pipe. In this field, the pipes for containing fluids include two types: high-energy pipes and intermediate-energy pipes. All non-high-energy pipes are intermediate-energy pipes.

[0012] Further, in some embodiments, in system i, the event frequency IE of the high-energy pipe rupture and flooding = p i ×S i , where p i is the high-energy pipe rupture frequency, S i is the flooding source term of system i; the calculation method of p i is: when the diameter of the high-energy pipe ≤ 0.254 m, p i = 2.5×10 -5 times / year·m of the reactor; when the diameter of the high-energy pipe > 0.254 m, p i = 1.23×10 -5 times / year·m of the reactor; S i is the number of calculation units determined according to one or more of the high-energy pipe length, the number of welds, and the number of pipe sections.

[0013] Further, in some embodiments, the memory stores a calculation program, which can implement the high-energy pipe rupture and flooding risk assessment method provided in any of the foregoing embodiments when executed by the processor. Description of the Drawings

[0014] Figure 1 is a quantitative calculation flow chart of the high-energy pipe rupture and flooding risk in a nuclear power plant in an embodiment.

[0015] The purpose of the above drawings is to make a detailed description of the present invention so that those skilled in the art can understand the technical concept of the present invention, rather than to limit the present invention. Detailed Embodiments

[0016] The present invention will be further described in detail below through specific embodiments in conjunction with the drawings.

[0017] As used herein, the term "embodiment" means that a particular feature, structure, or characteristic described in connection with an embodiment can be included in at least one embodiment of the present disclosure. The phrase appearing at various positions in the specification does not necessarily refer to the same embodiment, nor is it limited to mutually exclusive, independent, or alternative embodiments. Those skilled in the art should be able to understand that the embodiments herein can be combined with other embodiments without structural conflicts. In the description herein, the meaning of "a plurality of" is at least two.

[0018] Due to the particularity of nuclear energy, the safety of nuclear power plants is particularly sensitive. Nuclear power plants have complex structures and high safety requirements. There are a large number of high-energy pipelines inside nuclear power plants, and high-temperature or high-pressure flowing media flow inside these high-energy pipelines. Usually, these pipelines are part of various high-energy systems, or the internal temperature of the pipelines is higher than 95°C or the normal operating pressure is greater than 1.9 MPa during normal operation. Once a high-energy pipeline breaks, the leaked high-pressure fluid will exert a very high lateral force on the pipeline, and the pipeline that undergoes whipping may cause serious damage to surrounding equipment, pipelines, and structures. At the same time, the leaked fluid itself will cause drastic changes in environmental conditions, inducing further failures. Therefore, fully considering the breakage of high-energy pipelines and analyzing their subsequent effects helps improve the accuracy of nuclear power plant safety assessments. However, the conventional internal flooding probabilistic safety assessment method (PSA) does not include secondary accidents caused by the rupture of high-energy pipelines in the scope of investigation, resulting in insufficient completeness of the safety analysis method.

[0019] To solve the above problems, an embodiment of one aspect of the present invention provides a method for assessing the flooding risk caused by the rupture of high-energy pipelines in a nuclear power plant. The flow of this method is as Figure 1 shown and includes the following steps:

[0020] First, provide the initial information of all high-energy pipelines in the nuclear power plant. The initial information includes spatial distribution information, pipeline pressure, pipeline length, flow rate, and protection conditions. At the same time, provide the location information and environmental tolerance information of the target SSCs (structures, systems, and equipment in the nuclear power plant that, if they fail, will cause the nuclear power plant accident to deteriorate further or cause the failure of accident mitigation measures) in the nuclear power plant, such as important pumps, valves, or other electrical equipment, and the corresponding temperature, pressure, and humidity conditions that they can tolerate.

[0021] Next, based on the initial information of the high-energy pipelines, analyze the impact effects when each high-energy pipeline ruptures, and the impact of the impact effects on the target SSCs. In a preferred embodiment, specifically, the impact effects include one or more of the pipeline whipping impact effect, jet impact effect, fluid pressure relief transient effect, compartment pressurization effect, environmental condition deterioration effect, and flooding effect.

[0022] Next, based on the impact effects when the high-energy pipeline ruptures determined in the previous step, determine the accident initiating events caused by the ruptures of different high-energy pipelines.

[0023] Next, calculate the event frequency of the high-energy pipeline rupture, and then determine the frequency of each accident initiating event.

[0024] Finally, establish a flooding probabilistic safety assessment model (PSA model) for the nuclear power plant. Substitute the initiating events caused by the ruptures of different high-energy pipelines into the PSA model, simulate the consequences caused by different initiating events through the PSA model, and obtain the core damage frequency (CDF). Characterize the flooding risk after the high-energy pipeline rupture through the core damage frequency.

[0025] In a preferred embodiment, the process of quantitatively calculating the flooding risk of high-energy pipeline ruptures in a nuclear power plant is as follows:

[0026] Step 1: Collect information on the target SSCs and high-energy pipelines in the nuclear power plant. Among them, the high-energy pipeline information includes the spatial distribution information of the high-energy pipelines, pipeline pressure, temperature, length, flow rate information of the fluid in the high-energy pipelines, and pipeline protection measures (such as whether anti-ejection parts are set); the information of the target SSCs includes the location information of important SSCs and their environmental tolerance information, such as the maximum temperature, maximum pressure, corrosive medium state, environmental humidity, radioactivity, etc. that the important SSCs can tolerate without failure. The initial information of the high-energy pipelines and the target SSCs can be obtained according to the design scheme of the nuclear power plant, can also be obtained from the existing PSA system model, or can be directly measured through on-site inspections.

[0027] Step 2: Conduct an analysis of the impact effects of high-energy pipeline ruptures. In a nuclear power plant, according to the different installation positions and working states of high-energy pipelines, the possible impact effects during a rupture may include pipeline whipping effect, jet impact effect, fluid pressure relief transient effect, compartment pressurization effect, environmental condition deterioration effect, and flooding effect. These effects can cause the surrounding pipelines or target SSCs to fail, leading to secondary accidents.

[0028] Specifically, for the analysis of the impact of pipe whipping, if anti-whipping components are installed on the high-energy pipeline to provide additional reinforcement to the pipe body itself, it is considered that no secondary events will occur due to the whipping effect after the pipeline rupture; for high-energy pipelines without anti-whipping components, the impact of secondary damage to the associated pipelines (including high-energy and medium-energy pipelines arranged in the same space) within the whipping range of the high-energy pipeline (usually not exceeding the length of the high-energy pipeline being analyzed) needs to be considered. If secondary damage occurs to the associated pipelines, it will bring additional fluid increment to the compartment (such as the room where equipment is installed). The consequences caused by the whipping of the high-energy pipeline need to comprehensively consider the pipe diameter of the high-energy pipeline and the pipe diameter of the impacted associated pipeline. When the pipe diameter of the whipped pipeline is smaller than that of the high-energy pipeline causing the whipping, the secondary damage is manifested as circumferential or longitudinal rupture of the associated pipeline; when the pipe diameter of the whipped pipeline is not smaller than that of the high-energy pipeline causing the whipping, the secondary damage is manifested as a through crack in the associated pipeline. For circumferential or longitudinal rupture, the break area Ac of the secondary damage = πD1 2 / 4, where D1 is the inner diameter of the pipeline with secondary damage; for through crack, the break area Ac of the secondary damage = D1T / 4, where D1 is the inner diameter of the pipeline with secondary damage and T is the wall thickness.

[0029] For the analysis of the impact effect of jet flow, it is necessary to determine the spatial distribution of the jet flow formed after rupture based on the initial information of the high-energy pipeline (fluid pressure, flow rate, and temperature) (the jet flow distribution calculated according to the fluid properties, and whether there are barriers forming blockages in the distribution space, etc.). For the target SSC within the jet cone and jet fan formed by the high-temperature or subcooled jet flow at high pressure after the break, the failure determination is based on the distance d between the target SSC and the break and the diameter D of the high-energy pipeline. Based on a large amount of engineering experience, in the preferred embodiment, one criterion is: the target SSC with d ≤ 10D is determined to have failed, while the target SSC with d > 10D is determined not to have failed.

[0030] For the analysis of the impact effect of fluid pressure relief transient, when two or more high-energy pipelines are completely independent of each other or isolated by normally closed valves such as electric valves, pneumatic valves, or manual valves, it can be considered that the fluid pressure relief transient only causes the failure of the system where the ruptured high-energy pipeline is located, while for high-energy pipelines connected by normally open valves, it is considered that when one of them ruptures, the other connected high-energy pipelines will also fail.

[0031] For the analysis of the influence effects of compartment pressurization and environmental condition deterioration, the analysis is carried out on a compartment basis. For example, in the same room or a group of interconnected spaces, first, based on the initial information of the high-energy pipeline, determine the influence on the pressure and environmental conditions in the compartment due to fluid leakage when a rupture occurs. For example, the pressure increase caused by the leakage of high-pressure steam, the temperature change caused by the leakage of high-temperature steam, the chemical corrosion caused by the leakage of corrosive gas, the decline in insulation performance caused by the increase in environmental humidity, and the radioactive nuclide contamination caused by the leakage of radioactive gas, etc. Then, judge whether failure occurs according to the environmental tolerance performance of the target SSC in the compartment. For the target SSC that has not undergone the corresponding environmental tolerance performance evaluation, it should be conservatively determined to be completely failed. In one embodiment, for an electric valve in the same room as the main steam pipeline of a nuclear power plant, after the main steam pipeline ruptures and is affected by high-temperature and high-pressure steam, if it has not undergone the evaluation of high-temperature and high-pressure working conditions, it should be determined that the electric valve fails. However, if the working conditions of the corresponding high-temperature and high-pressure steam environment after environmental condition identification do not exceed the allowable environmental conditions of the electric valve, it is determined that the electric valve has not failed.

[0032] For the analysis of the influence effect of flooding, it is necessary to comprehensively consider the primary event of the rupture of the high-energy pipeline and the secondary rupture of the associated pipeline caused by the whipping influence effect. The secondary ruptured pipeline may include a high-energy pipeline or a medium-energy pipeline (i.e., a pipeline that accommodates fluid other than the high-energy pipeline). The evaluation of the flooding influence effect first determines the flow rate of the pipeline rupture. In a preferred embodiment, the break flow rate W of the high-energy pipeline rupture is W = 2C D A BR G C , where W is the mass flow rate, C D is the discharge coefficient, A BR is the break area, G C is the critical mass velocity; the volume flow rate Q I of the medium-energy pipeline rupture = A c (2ΔPg / Kρ) 0.5 , where Q I is the volume flow rate, T is the wall thickness of the pipe, D I is the inner diameter of the pipe, g is a given calculation coefficient, ΔP is the pipeline pressure, K is the loss coefficient, ρ is the density of the fluid in the pipeline, and the calculation coefficient g and the loss coefficient K can be determined according to the specific parameters of the ruptured pipeline combined with well-known engineering knowledge. After determining the flow rate of the pipeline rupture, further evaluate the total effect after the flooding spreads according to the location of the pipeline rupture and the environmental conditions, calculate the flooding water level, and determine the list of target SSCs that fail due to the flooding influence and the corresponding consequences according to the location information and environmental tolerance information of the target SSCs.

[0033] Step 3: Analysis of initiating events caused by high-energy pipe rupture. After analyzing all high-energy pipes within the analysis scope for the above-mentioned pipe whipping effect, jet impact effect, fluid pressure relief transient effect, compartment pressurization effect, environmental condition deterioration effect, and flooding effect, it is possible to further determine the failure conditions of the target SSCs caused by different high-energy pipe ruptures as initiating events, and based on this, establish an event tree to determine the consequences that each initiating event can lead to.

[0034] Step 4: Calculation of high-energy pipe rupture frequency. The frequency of high-energy pipe rupture flooding events can be calculated through the quantitative calculation formula IE = p i ×S i where IE is the frequency of high-energy pipe rupture flooding events, p i is the high-energy pipe rupture frequency, and S i is the flooding source term of system i; according to a large amount of engineering experience of the present invention, the calculation method of p i is: when the diameter of the high-energy pipe ≤ 0.254 m, p i = 2.5 × 10 -5 times / year per m of the reactor; when the diameter of the high-energy pipe > 0.254 m, p i = 1.23 × 10 -5 times / year per m of the reactor; S i is the number of calculation units determined according to one or more of the high-energy pipe length, the number of welds, and the number of pipe sections. For example, for an integral high-energy pipe without joints, S i is the pipe length (m) within the analysis area; for high-energy pipes with welds or mechanical connections, it is converted into an equivalent length (m) according to the material, service conditions, size, connection measures, etc. of the pipe. The conversion ratio can adopt the public data in the existing database or can be determined by targeted simulation tests.

[0035] Step 5: Model establishment and quantitative calculation. For the high-energy pipe rupture flooding risk, the core damage frequency (CDF) commonly used in the nuclear power field is used for quantitative characterization. Specifically, using general or special nuclear power PSA software, establish the corresponding nuclear power plant model, substitute the high-energy pipe initiating events obtained in Step 3 (including the primary event of high-energy pipe rupture and the secondary events triggered by high-energy pipe rupture) into the PSA model, calculate the conditional core damage probability (CCDP) caused by high-energy pipe rupture, and then substitute the high-energy pipe rupture frequency obtained in Step 4 to calculate the core damage frequency (CDF) caused by high-energy pipe rupture, thereby determining the overall impact of the high-energy pipe rupture flooding accident on the safety of the nuclear power plant.

[0036] In a preferred embodiment, the method for evaluating the risk of flooding caused by the rupture of high-energy pipelines in a nuclear power plant provided in the above embodiment can be written as a calculation program in a general-purpose software (such as risk spectrum) or a specially developed dedicated software and stored in the memory of a computing device. When the calculation program is executed by the processor of the computing device, the method for evaluating the risk of flooding caused by the rupture of high-energy pipelines in the above embodiment can be implemented. In different embodiments, the computing device can be a general-purpose computer, a specially built dedicated computing device, a virtual computer, a cloud computing device, etc. In different embodiments, when implementing this method in a computing device, different high-energy pipelines, an initial information database of target SSCs, or different initiating event databases can be pre-entered into the computer, and the simulation calculation process can be automatically retrieved and executed through the calculation program to batch obtain the CDF calculation results under different conditions; alternatively, during the execution of some steps, calculation parameters can be manually input into the calculation program to complete the CDF calculation.

[0037] The purpose of the above embodiment is to further elaborate on the present invention with reference to the accompanying drawings so that those skilled in the art can understand the technical concept of the present invention. Within the scope disclosed by the present invention, optimizing or equivalently replacing the involved method steps, and combining the implementation manners in different embodiments without conflict in structure and principle all fall within the protection scope of the present invention.

Claims

1. A method for assessing the risk of flooding caused by the rupture of high-energy pipelines in a nuclear power plant, characterized in that, The method includes the following steps: Providing initial information of high-energy pipelines in a nuclear power plant, where the initial information includes spatial distribution information, pipeline pressure, pipeline length, flow rate, and protection conditions, and providing location information and environmental tolerance information of a target SSC in the nuclear power plant; Analyzing the influence effects of the rupture of each high-energy pipeline and the influence of the influence effects on the target SSC according to the initial information; Determining initiating events caused by the rupture of different high-energy pipelines according to the influence of the influence effects on the target SSC; Establishing a flooding probability safety assessment model for the interior of the nuclear power plant, substituting the initiating events caused by the rupture of different high-energy pipelines into the flooding probability safety assessment model for the interior of the nuclear power plant, and providing the frequency of each initiating event, and calculating the core damage frequency caused by the flooding accident due to the rupture of the high-energy pipeline; In the evaluation of the waterlogging impact effect, the break flow rate W of the high-energy pipeline rupture is W = 2C D A BR G C , where W is the mass flow rate, C D is the discharge coefficient, A BR is the break area, G C is the critical mass velocity; the volume flow rate Q of the medium-energy pipeline rupture I = A c (2ΔPg / Kρ) 0.5 , where Q I is the volume flow rate, A c = D I T / 4, T is the wall thickness, D I is the inner diameter of the pipeline, g is a given calculation coefficient, ΔP is the pipeline pressure, K is the loss coefficient, and ρ is the fluid density inside the pipeline; In system i, the event frequency IE of high-energy pipeline rupture and flooding is IE = p i ×S i , where p i is the high-energy pipeline rupture frequency, and S i is the flooding source term of system i; p i The calculation method is as follows: when the diameter of the high-energy pipeline ≤ 0.254 m, p i = 2.5 × 10 -5 times / year per m of the reactor; when the diameter of the high-energy pipeline > 0.254 m, p i = 1.23 × 10 -5 times / year per m of the reactor; S i is the number of calculation units determined according to one or more of the high-energy pipeline length, the number of welds, and the number of pipeline sections.

2. The method for evaluating the risk of flooding caused by the rupture of high-energy pipelines in a nuclear power plant according to claim 1, wherein The influence effects include one or a combination of more of a pipeline whipping influence effect, a jet impact influence effect, a fluid depressurization transient influence effect, a compartment pressurization influence effect, an environmental condition deterioration influence effect, and a flooding influence effect.

3. The method for evaluating the risk of flooding caused by the rupture of high-energy pipelines in a nuclear power plant according to claim 2, wherein, The pipeline whipping influence effect includes the associated pipeline rupture caused by whipping during the rupture of the high-energy pipeline, and the associated pipeline includes pipelines within the whipping range of the high-energy pipeline without anti-whipping components; wherein, the associated pipeline rupture includes circumferential / longitudinal pipeline rupture and through cracks, the circumferential / longitudinal pipeline rupture occurs in the associated pipeline with a diameter smaller than that of the high-energy pipeline where the rupture occurs, and the through cracks occur in the associated pipeline with a diameter not less than that of the high-energy pipeline where the rupture occurs.

4. The method for evaluating the risk of flooding caused by the rupture of high-energy pipelines in a nuclear power plant according to claim 3, wherein, The break flow area of the circumferential / longitudinal pipe rupture is πD1 2 / 4, where D1 is the inner diameter of the pipe; the break flow area of the through crack is D1T / 4, where D1 is the inner diameter of the pipe and T is the wall thickness of the pipe.

5. The method for evaluating the risk of flooding caused by the rupture of high-energy pipelines in a nuclear power plant according to claim 2, wherein, The evaluation method for the jet impact influence effect is: according to the initial information of the high-energy pipeline, determining the spatial distribution of the jet flow generated when a break occurs in the high-energy pipeline, and determining that the target SSC satisfying d≤10D fails, and determining that the target SSC satisfying d>10D does not fail, where d is the distance between the target SSC within the spatial distribution of the jet flow and the break of the high-energy pipeline, and D is the diameter of the high-energy pipeline.

6. The method for evaluating the risk of flooding caused by the rupture of high-energy pipelines in a nuclear power plant according to claim 2, wherein The evaluation methods for the compartment pressurization influence effect and the environmental condition deterioration influence effect are: according to the initial information of the high-energy pipeline, determining the pressure change and environmental condition change of the compartment where the high-energy pipeline is located when a break occurs in the high-energy pipeline, and determining whether the target SSC fails according to the environmental tolerance information of the target SSC in the compartment where the high-energy pipeline is located, and the environmental conditions include one or a combination of more of temperature, humidity, environmental atmosphere, and radionuclides.

7. A computing device, comprising a memory and a processor, characterized in that, The memory stores a calculation program, and when the calculation program is executed by the processor, it can implement the method for assessing the flooding risk caused by the rupture of high-energy pipelines in a nuclear power plant as described in any one of claims 1 to 6.

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