Emergency risk index value determination method and device, and nuclear power plant site determination method and system based on emergency recommendation

Abstract

The invention discloses an emergency risk index value determination method and device, and a nuclear power plant site determination method and system based on emergency recommendation, and relates to the technical field of nuclear industry. The emergency risk index determination method comprises the following steps: acquiring a collective effective dose of a planned plant address in a target area, a source item unit power of a preset normalized source item, a plant address unit power of the planned plant address and a target reactor core damage frequency; and according to the collective effective dose, the source item unit power, the site unit power and the target core damage frequency, determining an emergency risk index value of the proposed site. According to the embodiment of the invention, the method can perform quantitative analysis on the emergency feasibility of the planned site of the nuclear power plant, and also can improve the accuracy of emergency feasibility analysis of the planned site of the nuclear power plant, thereby improving the accuracy of site determination of the nuclear power plant.

Description

Technical Field

[0001] The present application belongs to the field of nuclear industry technology, and specifically relates to a method and device for determining an emergency risk index value, and a method and system for determining a nuclear power plant site based on emergency recommendations. Background Art

[0002] In the nuclear power plant site selection stage, it is necessary to analyze and evaluate the feasibility of the nuclear power plant to implement the emergency plan, that is, to evaluate the emergency conditions of the site. The "Safety Regulations for Nuclear Power Plant Site Evaluation" states that "the feasibility of emergency response actions must be evaluated, and factors related to the site must be considered during the evaluation: population and distribution characteristics, special geographical characteristics, agricultural, ecological and environmental characteristics of the area where the site is located, etc."

[0003] During the site selection phase of a nuclear power plant, the emergency conditions of the site should be considered and evaluated, and the feasibility of implementing the accident emergency plan should be demonstrated. In addition to the population distribution characteristics and atmospheric dispersion conditions around the site, the safety characteristics of the reactor itself are also important factors affecting the feasibility of nuclear power plant emergencies. According to the relevant provisions of the national standard GB6249, the indicators for evaluating the emergency conditions of the site during the site selection phase include the population distribution in non-residential areas and planned restricted areas, the personal effective dose at the boundaries of non-residential areas and planned restricted areas, and the collective effective dose of the public at the site. These indicators focus on reflecting the impact of population distribution and atmospheric dispersion conditions on site emergencies, and fail to fully reflect the impact of the safety characteristics of the reactor itself on site emergencies.

[0004] At present, the emergency feasibility of the proposed sites of nuclear power plants is qualitatively analyzed based on the above-mentioned population distribution characteristics and atmospheric dispersion conditions. The proposed sites of nuclear power plants are highly subjective and fail to fully reflect the impact of the safety characteristics of the reactor itself on the site emergency, resulting in low accuracy in the emergency feasibility analysis of the proposed sites of nuclear power plants, which in turn leads to low accuracy in the determination of the sites of nuclear power plants. Summary of the invention

[0005] The technical problem to be solved by the present application is to provide a method and device for determining an emergency risk index value, and a method and system for determining a nuclear power plant site based on emergency recommendation in view of the above-mentioned deficiencies in the prior art. The method can quantitatively analyze the emergency feasibility of the proposed site of the nuclear power plant, and improve the accuracy of the emergency feasibility analysis of the proposed site of the nuclear power plant, thereby improving the accuracy of the determination of the site of the nuclear power plant.

[0006] In a first aspect, an embodiment of the present application provides a method for determining an emergency risk index value, comprising:

[0007] Obtain the collective effective dose of the proposed site in the target area, the source unit power of the preset normalized source term, the site unit power of the proposed site and the target core damage frequency;

[0008] The emergency risk index value of the proposed site is determined based on the collective effective dose, source unit power, site unit power and target core damage frequency.

[0009] In some embodiments of the first aspect, obtaining a collective effective dose of the proposed site within a target area includes:

[0010] Obtain n*m sub-areas of the target area, preset normalized source terms, respiratory rate and dose conversion factor, where n and m are both positive integers greater than or equal to 1;

[0011] For each of the n*m ​​sub-areas, obtain the population number and atmospheric diffusion factor corresponding to the sub-area to obtain n*m population numbers and n*m atmospheric diffusion factors;

[0012] The collective effective dose of the proposed site in the target area is determined based on the preset normalized source terms, breathing rate and dose conversion factors, n*m population numbers and n*m atmospheric dispersion factors.

[0013] In some implementations of the first aspect, obtaining n*m sub-areas of the target area includes:

[0014] Divide the target area into n*m sub-areas according to n preset radial distances and m radial directions;

[0015] and / or, obtain respiration rate, including:

[0016] The respiration rate is obtained from the Technical Specification for Environmental Impact Assessment of Release of Airborne Radioactive Materials in Accident Conditions of Nuclear Power Plants NB / T 20182-2012;

[0017] and / or, obtain dose conversion factors, including:

[0018] Get the dose conversion factor from the basic standard for ionizing radiation protection and radiation source safety GB18871;

[0019] And / or, obtain the atmospheric dispersion factor corresponding to the sub-area, including:

[0020] The Gaussian plume model is used to determine the atmospheric dispersion factor corresponding to the sub-area.

[0021] In some embodiments of the first aspect, determining the collective effective dose of the proposed site in the target area according to a preset normalized source term, a respiration rate and a dose conversion factor, n*m population numbers and n*m atmospheric dispersion factors comprises:

[0022] Substitute the preset normalized source term, breathing rate and dose conversion factor, n*m population and n*m atmospheric dispersion factors into formula (1) to calculate the collective effective dose of the proposed site in the target area;

[0023] Formula (1) includes:

[0024]

[0025] Among them, D T It represents the collective effective dose of the proposed site within the target area; It represents the atmospheric diffusion factor of the sub-area corresponding to the j-th radial direction at the r-th preset radial distance; Q represents the preset normalized source term; BR represents the breathing rate; DFI represents the dose conversion factor; P(r,j) represents the population size of the sub-area corresponding to the j-th radial direction at the r-th preset radial distance; 1≤r≤n, 1≤j≤m.

[0026] In some implementations of the first aspect, obtaining a target core damage frequency includes:

[0027] According to the first-level probabilistic safety analysis of the nuclear power plant, the target core damage frequency is determined.

[0028] In some implementations of the first aspect, determining the emergency risk index value of the proposed site according to the collective effective dose, the source term unit power, the site unit power and the target core damage frequency includes:

[0029] Substitute the collective effective dose, source unit power, site unit power and target core damage frequency into formula (2) to calculate the emergency risk index value of the proposed site;

[0030] Formula (2) includes:

[0031]

[0032] Among them, D TW Indicates the emergency risk index value of the proposed site; D T W represents the collective effective dose of the proposed site in the target area; s Indicates source unit power; W r represents the unit power at the site; CDF represents the target core damage frequency.

[0033] Based on the same inventive concept, in a second aspect, the embodiment of the present application further provides a method for determining a nuclear power plant site based on emergency recommendation, comprising:

[0034] According to any one of the emergency risk index value determination methods in the first aspect, p emergency risk index values ​​corresponding to p proposed plant sites are determined, where p is a positive integer;

[0035] According to p emergency risk index values, q nuclear power plant sites are determined from p proposed sites, 1≤q≤p.

[0036] In some implementations of the second aspect, determining q nuclear power plant sites from p proposed sites according to p emergency risk index values ​​includes:

[0037] For each of the p proposed plant sites, determine the relative risk ranking of the emergency risk index value corresponding to the proposed plant site in all the emergency risk index values ​​to obtain p relative risk rankings;

[0038] In the case where p relative risk rankings are ranked from large to small according to the emergency risk index values, the q proposed sites corresponding to the last q emergency risk index values ​​in the p relative risk rankings are determined as the q nuclear power plant sites;

[0039] When p relative risk rankings are ranked from small to large according to the emergency risk index values, q proposed sites corresponding to the first q emergency risk index values ​​in the p relative risk rankings are determined as q nuclear power plant sites.

[0040] Based on the same inventive concept, in a third aspect, an embodiment of the present application further provides an emergency risk index value determination device, comprising:

[0041] The first acquisition module is used to obtain the collective effective dose of the proposed site in the target area, the source item unit power of the preset normalized source item, the site unit power of the proposed site and the target core damage frequency;

[0042] The first determination module is used to determine the emergency risk index value of the proposed site based on the collective effective dose, source unit power, site unit power and target core damage frequency.

[0043] In some implementations of the third aspect, the first acquisition module is specifically configured to:

[0044] Obtain n*m sub-areas of the target area, preset normalized source terms, respiratory rate and dose conversion factor, where n and m are both positive integers greater than or equal to 1;

[0045] For each of the n*m ​​sub-areas, obtain the population number and atmospheric diffusion factor corresponding to the sub-area to obtain n*m population numbers and n*m atmospheric diffusion factors;

[0046] The collective effective dose of the proposed site in the target area is determined based on the preset normalized source terms, breathing rate and dose conversion factors, n*m population numbers and n*m atmospheric dispersion factors.

[0047] In some implementations of the third aspect, the first acquisition module is specifically configured to:

[0048] Substitute the preset normalized source term, breathing rate and dose conversion factor, n*m population and n*m atmospheric dispersion factors into formula (1) to calculate the collective effective dose of the proposed site in the target area;

[0049] Formula (1) includes:

[0050]

[0051] Among them, D T It represents the collective effective dose of the proposed site within the target area; It represents the atmospheric diffusion factor of the sub-area corresponding to the j-th radial direction at the r-th preset radial distance; Q represents the preset normalized source term; BR represents the breathing rate; DFI represents the dose conversion factor; P(r,j) represents the population size of the sub-area corresponding to the j-th radial direction at the r-th preset radial distance; 1≤r≤n, 1≤j≤m.

[0052] In some implementations of the third aspect, the first determining module is specifically configured to:

[0053] Substitute the collective effective dose, source unit power, site unit power and target core damage frequency into formula (2) to calculate the emergency risk index value of the proposed site;

[0054] Formula (2) includes:

[0055]

[0056] Among them, D TW Indicates the emergency risk index value of the proposed site; D T W represents the collective effective dose of the proposed site in the target area; s Indicates source unit power; W r represents the unit power at the site; CDF represents the target core damage frequency.

[0057] Based on the same inventive concept, in a fourth aspect, the embodiment of the present application further provides a system for determining a nuclear power plant site, including:

[0058] As in any one of the third aspects, the device for determining an emergency risk index value is used to determine p emergency risk index values ​​corresponding to p proposed plant sites, where p is a positive integer;

[0059] The nuclear power plant site determination device is connected to the emergency risk index value determination device and is used to determine q nuclear power plant sites from p proposed sites according to p emergency risk index values, 1≤q≤p.

[0060] In some implementations of the fourth aspect, the nuclear power plant site determination device is specifically used to:

[0061] For each of the p proposed plant sites, determine the relative risk ranking of the emergency risk index value corresponding to the proposed plant site in all the emergency risk index values ​​to obtain p relative risk rankings;

[0062] In the case where p relative risk rankings are ranked from large to small according to the emergency risk index values, the q proposed sites corresponding to the last q emergency risk index values ​​in the p relative risk rankings are determined as the q nuclear power plant sites;

[0063] When p relative risk rankings are ranked from small to large according to the emergency risk index values, q proposed sites corresponding to the first q emergency risk index values ​​in the p relative risk rankings are determined as q nuclear power plant sites.

[0064] According to the method and device for determining the emergency risk index value and the method and system for determining the site of a nuclear power plant based on emergency recommendation provided in the embodiments of the present application, by obtaining the collective effective dose of the proposed site in the target area, the source item unit power of the preset normalized source item, the site unit power of the proposed site and the target core damage frequency, the emergency risk index value of the proposed site can be determined based on the collective effective dose, the source item unit power, the site unit power and the target core damage frequency. In the embodiment of the present application, since the source-term unit power, the site unit power and the target core damage frequency can reflect the impact of the safety characteristics of the reactor itself on the site emergency, the emergency risk index value of the proposed site determined by the collective effective dose, the source-term unit power, the site unit power and the target core damage frequency can reflect the impact of the safety characteristics of the reactor itself on the site emergency while conducting a quantitative analysis of the emergency feasibility of the proposed site of the nuclear power plant, thereby improving the accuracy of the emergency risk index value of the proposed site, that is, improving the accuracy of the emergency feasibility analysis of the proposed site of the nuclear power plant, thereby improving the accuracy of the determination of the site of the nuclear power plant. BRIEF DESCRIPTION OF THE DRAWINGS

[0065] Figure 1 A schematic diagram showing a flow chart of a method for determining an emergency risk index value provided in an embodiment of the present application;

[0066] Figure 2 A schematic diagram showing the collective effective dose within the target area of ​​the proposed plant site provided in an embodiment of the present application;

[0067] Figure 3 A schematic diagram of a flow chart of a method for determining a nuclear power plant site based on emergency recommendation provided in an embodiment of the present application is shown;

[0068] Figure 4 A segmented statistical diagram showing emergency risk index values ​​of multiple proposed plant sites provided in an embodiment of the present application;

[0069] Figure 5 Another schematic diagram of a process for determining a nuclear power plant site based on emergency recommendation provided in an embodiment of the present application is shown;

[0070] Figure 6 A schematic diagram showing a structure of an emergency risk index value determination device provided in an embodiment of the present application;

[0071] Figure 7 A structural schematic diagram of a nuclear power plant site determination system based on emergency recommendation provided in an embodiment of the present application is shown. DETAILED DESCRIPTION

[0072] In order to enable those skilled in the art to better understand the technical solution of the present application, the present application is further described in detail below with reference to the accompanying drawings and embodiments.

[0073] The features and exemplary embodiments of various aspects of the present application will be described in detail below. In order to make the purpose, technical solutions and advantages of the present application clearer, the present application will be further described in detail below in conjunction with the accompanying drawings and specific embodiments. It should be understood that the specific embodiments described herein are only configured to explain the present application and are not configured to limit the present application. For those skilled in the art, the present application can be implemented without the need for some of these specific details. The following description of the embodiments is only to provide a better understanding of the present application by illustrating the examples of the present application.

[0074] It should be noted that, in this article, relational terms such as first and second, etc. are only used to distinguish one entity or operation from another entity or operation, and do not necessarily require or imply any such actual relationship or order between these entities or operations. Moreover, the terms "include", "comprise" or any other variants thereof are intended to cover non-exclusive inclusion, so that a process, method, article or device including a series of elements includes not only those elements, but also other elements not explicitly listed, or also includes elements inherent to such process, method, article or device. In the absence of further restrictions, the elements defined by the statement "include..." do not exclude the presence of other identical elements in the process, method, article or device including the elements.

[0075] It should be understood that the term "and / or" used in this article is only a description of the association relationship of associated objects, indicating that there can be three relationships. For example, A and / or B can represent: A exists alone, A and B exist at the same time, and B exists alone. In addition, the character " / " in this article generally indicates that the associated objects before and after are in an "or" relationship.

[0076] Example 1

[0077] Figure 1A flow chart showing a method for determining an emergency risk indicator value provided in an embodiment of the present application is shown.

[0078] The emergency risk index value determination method provided in the embodiment of the present application can be executed by an electronic device and an emergency risk index value determination device, etc. The following is an example of the emergency risk index value determination method being executed by an electronic device.

[0079] like Figure 1 As shown, the method for determining the emergency risk index value provided in the embodiment of the present application may include steps S110 to S120.

[0080] S110, obtaining the collective effective dose of the proposed site in the target area, the source item unit power of the preset normalized source item, the site unit power of the proposed site and the target core damage frequency.

[0081] S120. Determine the emergency risk index value of the proposed site based on the collective effective dose, source unit power, site unit power and target core damage frequency.

[0082] According to the method for determining the emergency risk index value provided in the embodiment of the present application, by obtaining the collective effective dose of the proposed site in the target area, the source term unit power of the preset normalized source term, the site unit power of the proposed site and the target core damage frequency, the emergency risk index value of the proposed site can be determined based on the collective effective dose, the source term unit power, the site unit power and the target core damage frequency.

[0083] In the embodiment of the present application, since the source-term unit power, the site unit power and the target core damage frequency can reflect the impact of the safety characteristics of the reactor itself on the site emergency, the emergency risk index value of the proposed site determined by the collective effective dose, the source-term unit power, the site unit power and the target core damage frequency can reflect the impact of the safety characteristics of the reactor itself on the site emergency while conducting a quantitative analysis of the emergency feasibility of the proposed site of the nuclear power plant, thereby improving the accuracy of the emergency risk index value of the proposed site, that is, improving the accuracy of the emergency feasibility analysis of the proposed site of the nuclear power plant, thereby improving the accuracy of the determination of the site of the nuclear power plant.

[0084] The specific implementation methods of the above steps are introduced below.

[0085] In step S110, the proposed plant site may be a location that is considered to be potentially feasible after preliminary evaluation and comparison during the site selection process of the nuclear power plant.

[0086] The target area may include an area with the center of the proposed plant site as the center and a preset radial distance as the radius. The preset radial distance can be set according to actual conditions and is not limited here. For example, the preset radial distance can be 10km, 20km, 30km and 50km, etc.

[0087] The collective effective dose may be the collective effective dose of the proposed plant site in the target area, and its unit may be person·Sv.

[0088] The preset normalized source terms can be used to evaluate the radiation safety performance of nuclear power plants.

[0089] The source term unit power may include the unit power corresponding to the preset normalized source term, and the unit power may include the rated electric power when the nuclear power plant is in operation.

[0090] The unit power at the plant site may include the unit power corresponding to the plant site.

[0091] The target core damage frequency may include the core damage frequency of the reactor model, that is, the frequency of serious accidents that cause serious damage or even melting of the reactor core, with the unit of (reactor·year)-1.

[0093] In some embodiments, obtaining the collective effective dose of the proposed site within the target area may include:

[0094] Obtain n*m sub-areas of the target area, preset normalized source terms, respiratory rate and dose conversion factor, where n and m are both positive integers greater than or equal to 1;

[0095] For each of the n*m ​​sub-areas, obtain the population number and atmospheric diffusion factor corresponding to the sub-area to obtain n*m population numbers and n*m atmospheric diffusion factors;

[0096] The collective effective dose of the proposed site in the target area is determined based on the preset normalized source terms, breathing rate and dose conversion factors, n*m population numbers and n*m atmospheric dispersion factors.

[0097] n may be the number of preset radial distances, and m may be the number of radiation directions.

[0098] It should be noted that the values ​​of n and m can be set according to actual conditions and are not limited here. n and m can be equal or unequal. For example, n=m=1, n=30, m=16, etc.

[0099] In some examples, obtaining n*m sub-areas of the target area may include:

[0100] The target area is divided into n*m sub-areas according to n preset radial distances and m radial directions.

[0101] In this embodiment, the target area is divided into n*m sub-areas based on n preset radial distances and m radial azimuths. This can fully consider the impact of preset radial distances and radial azimuths on the emergency analysis of the proposed site, thereby providing a basis for subsequently improving the accuracy of the emergency risk index value of the proposed site.

[0102] Specifically, the target area is divided into n intermediate areas with the center of the target area (i.e., the center of the proposed plant site) as the center of the circle and n preset radial distances as the radius; the n intermediate areas are then divided according to m radial directions to obtain n*m sub-areas. Alternatively, the target area may be first divided according to m radial directions to obtain m intermediate areas, and then the m intermediate areas may be divided according to n preset radial distances to obtain n*m sub-areas. Of course, the target area may also be divided according to n preset radial distances and m radial directions at the same time to obtain n*m sub-areas.

[0103] Exemplarily, the n preset radial distances may include 1 km, 2 km, 3 km, ..., 30 km; the m radial directions may include 16 radial directions, which can be divided into 480 sub-areas.

[0104] It should be noted that the n preset radial distances and the m radial directions can be set according to actual conditions and are not limited here. The unit of the preset radial distance can be m or km.

[0105] In another embodiment, the target area may also include a polygonal area centered on the center of the proposed plant site, and the proposed plant site may also divide the target area according to a preset area. For example, the target area may be a rectangle centered on the center of the proposed plant site with an area of ​​a*b, and the preset area may be ab / nm.

[0106] In some examples, obtaining the respiration rate may include:

[0107] The respiration rate was obtained from the Technical Specification for Environmental Impact Assessment of Radiation Release of Airborne Radioactive Materials in Accident Conditions of Nuclear Power Plants NB / T 20182-2012.

[0108] In this embodiment, the accuracy of the breathing rate can be improved by obtaining the breathing rate from the Technical Specification for Environmental Impact Assessment of Radiation Release of Airborne Radioactive Materials in Accident Conditions of Nuclear Power Plants NB / T 20182-2012.

[0109] The respiration rate can be the respiration rate of a person, and the unit can be m 3 / s.

[0110] In other examples, the breathing rate may be pre-stored in the electronic device for direct subsequent retrieval.

[0111] In some examples, obtaining a dose conversion factor may include:

[0112] The dose conversion factor was obtained from the basic standard for ionizing radiation protection and radiation source safety GB18871.

[0113] In this embodiment, the accuracy of the dose conversion factor can be improved by obtaining the dose conversion factor from the basic standard for ionizing radiation protection and radiation source safety GB18871.

[0114] The dose conversion factor may be the dose or dose rate generated in a given material by the particle fluence or particle fluence rate at a certain point in the material, and its unit may be Sv / Bq.

[0115] In other examples, the dosage conversion factor may be pre-stored in the electronic device for subsequent direct retrieval.

[0116] In some examples, obtaining a preset normalized source term may include:

[0117] The preset normalized source terms are obtained through accident analysis.

[0118] For example, the preset normalized source term can be obtained through accident analysis including mechanistic analysis such as containment leakage pathway and radionuclide removal.

[0119] The unit of the default normalized source term may be Bq.

[0120] In other examples, preset normalized source items may be pre-stored in the electronic device for subsequent direct call.

[0121] In some examples, the population number corresponding to the sub-area can be obtained through population surveys or the like, or the electronic device pre-stores the population number corresponding to each sub-area in the n*m ​​sub-areas for subsequent direct retrieval.

[0122] In some examples, obtaining the atmospheric diffusion factor corresponding to the sub-area may include:

[0123] The Gaussian plume model is used to determine the atmospheric dispersion factor corresponding to the sub-area.

[0124] In this embodiment, the Gaussian plume model is used to quickly and accurately determine the atmospheric diffusion factor corresponding to the sub-area.

[0125] The Gaussian plume model may be a mathematical model for calculating the downwind concentration of airborne pollutants in the atmosphere, and is an existing model.

[0126] The unit of atmospheric dispersion factor can be s / m 3 .

[0127] In other examples, the electronic device may pre-store the atmospheric diffusion factors corresponding to the sub-areas for subsequent direct retrieval.

[0128] In some examples, the collective effective dose of the proposed site in the target area is determined based on preset normalized source terms, breathing rate and dose conversion factors, n*m population numbers and n*m atmospheric dispersion factors, including:

[0129] Substitute the preset normalized source term, breathing rate and dose conversion factor, n*m population and n*m atmospheric dispersion factors into formula (1) to calculate the collective effective dose of the proposed site in the target area;

[0130] Formula (1) includes:

[0131]

[0132] Among them, D T It represents the collective effective dose of the proposed site within the target area; It represents the atmospheric diffusion factor of the sub-area corresponding to the j-th radial direction at the r-th preset radial distance; Q represents the preset normalized source term; BR represents the breathing rate; DFI represents the dose conversion factor; P(r,j) represents the population size of the sub-area corresponding to the j-th radial direction at the r-th preset radial distance; 1≤r≤n, 1≤j≤m.

[0133] In this embodiment, the collective effective dose of the proposed plant site in the target area can be quickly and accurately determined by the above formula (1), providing a basis for the subsequent determination of the emergency risk index value.

[0134] For example, taking the proposed site of Taohuajiang and the proposed site of Longyou as examples, the collective effective dose distribution in the target area of ​​the proposed site of Taohuajiang and the proposed site of Longyou is as follows: Figure 2 As shown. Among them, Figure 2 The horizontal axis and the vertical axis on the left represent the preset radial distance from the center of the proposed site, and the vertical axis on the right represents the collective effective dose corresponding to the proposed site. The target area is an area with a preset radial distance of 50km as the radius, with the center of the proposed site as the center. The collective effective dose of the proposed site in Taohuajiang is 4404.9 man·Sv, and the collective effective dose of the proposed site in Longyou is 2278 man·Sv.

[0135] In some examples, obtaining a target core damage frequency may include:

[0136] According to the first-level probabilistic safety analysis of the nuclear power plant, the target core damage frequency is determined.

[0137] In this embodiment, the target core damage frequency can be accurately determined through the first-level probabilistic safety analysis (PSA) of the nuclear power plant.

[0138] The first level of probabilistic safety analysis can be a system analysis method based on probability theory, which is used to determine the average risk based on the unavailability of the systems and components under consideration.

[0139] In other examples, the target core damage frequency may be pre-stored in the electronic device for subsequent direct retrieval.

[0140] In step S120, after obtaining the collective effective dose of the proposed site in the target area, the source item unit power of the preset normalized source item, the site unit power of the proposed site and the target core damage frequency, the electronic equipment can also determine the emergency risk index value of the proposed site based on the collective effective dose, the source item unit power, the site unit power and the target core damage frequency.

[0141] In some embodiments, determining the emergency risk index value of the proposed site based on the collective effective dose, source term unit power, site unit power, and target core damage frequency may include:

[0142] Substitute the collective effective dose, source unit power, site unit power and target core damage frequency into formula (2) to calculate the emergency risk index value of the proposed site;

[0143] Formula (2) includes:

[0144]

[0145] Among them, D TW Indicates the emergency risk index value of the proposed site; D T W represents the collective effective dose of the proposed site in the target area; s Indicates source unit power; W r represents the unit power at the site; CDF represents the target core damage frequency.

[0146] In this embodiment, the emergency risk index value of the proposed plant site can be determined quickly and accurately through the above formula (2).

[0147] It represents the collective effective dose produced per MWt of power.

[0148] The emergency risk index value of the proposed site can be the collective effective dose weighted by the unit power (i.e., source unit power and site unit power) and the core damage frequency (CDF, ​​i.e., target core damage frequency) within the target area of ​​the proposed site. The unit of the emergency risk index value can be man·Sv / reactor-year.

[0149] It should be noted that, in the embodiment of the present application, the smaller the emergency risk index value is, the better the emergency feasibility conditions of the proposed site are.

[0150] For example, taking the proposed sites of Taohuajiang and Longyou as examples, after weighting the collective effective dose by the core damage frequency and the actual power of the unit, the emergency risk index value within a radius of 50km for the proposed site of Taohuajiang is 5.29 man·Sv / reactor-year, and the emergency risk index value within a radius of 50km for the proposed site of Wan'an is 2.73 man·Sv / reactor-year.

[0151] In order to better understand the method for determining the emergency risk index value provided in the embodiment of the present application, a specific embodiment is described below.

[0152] The target area of ​​the proposed site A is divided into 20 sub-areas according to 10 preset radial distances and 2 radial directions. The populations of the above 20 sub-areas are 254, 286, 354, 368, 456, 501, 752, 801, 1060, 1085, 1325, 1301, 1651, 1664, 2030, 2062, 2489, 2500, 3020 and 3010 respectively; the atmospheric dispersion factors of the above 20 sub-areas are 3.16×10 -5 s / m 3 ,3.16×10 -5 s / m 3 , 1.12×10 -5 s / m 3 , 1.12×10 -5 s / m 3 , 0.61×10 -5 s / m 3 , 0.61×10 -5 s / m 3 , 0.40×10 -5 s / m 3 , 0.40×10 -5 s / m 3 , 0.30×10 -5 s / m 3 , 0.30×10 -5 s / m 3 , 0.22×10 -5 s / m 3 , 0.22×10 -5 s / m 3 , 0.17×10 -5 s / m 3 , 0.17×10 -5 s / m 3 , 0.14×10 -5 s / m 3 , 0.14×10 -5s / m 3 , 0.12×10 -5 s / m 3 , 0.12×10 -5 s / m 3 , 0.1×10 -5 s / m 3 , 0.1×10 -5 s / m 3 ; Respiration rate is 3.5×10 -4 m 3 / s; the dose conversion factor is 7.40e-09Sv / Bq; the default normalized source term is 2×10 11 Substituting the above 20 population numbers, 20 atmospheric diffusion factors, respiration rate, dose conversion factor and normalized source term into formula (1) for calculation, the collective effective dose of the proposed site A in the target area is 0.6790 person·s / m 3 ×2×10 11 Bq×3.5×10 -4 m 3 / s×7.40e-09Sv / Bq=0.351man·Sv. Assuming that the source unit power is 500MWt, the site unit power is 1000MWt, and the target core damage frequency is 1e-4, the collective effective dose, source unit power, site unit power and target core damage frequency are substituted into formula (2) for calculation, and the emergency risk index value of the proposed site is 0.001358man·Sv / reactor-year.

[0153] Based on the same inventive concept, an embodiment of the present application provides a method for determining a nuclear power plant site based on emergency recommendations. The method for determining a nuclear power plant site based on emergency recommendations provided by an embodiment of the present application is described below in conjunction with the accompanying drawings.

[0154] Example 2

[0155] Figure 3 A flow chart of a method for determining a nuclear power plant site based on emergency recommendation provided in an embodiment of the present application is shown.

[0156] The method for determining the site of a nuclear power plant based on emergency recommendations provided in the embodiment of the present application can be executed by electronic equipment and a device for determining the site of a nuclear power plant based on emergency recommendations, etc. The following is an example of the method for determining the site of a nuclear power plant based on emergency recommendations being executed by an electronic device.

[0157] like Figure 3 As shown, the method for determining the site of a nuclear power plant based on emergency recommendation provided in an embodiment of the present application may include steps S310 to S320.

[0158] S310. According to any one of the emergency risk index value determination methods in Example 1, p emergency risk index values ​​corresponding to p proposed plant sites are determined, where p is a positive integer.

[0159] S320. According to p emergency risk index values, determine q nuclear power plant sites from p proposed sites, 1≤q≤p.

[0160] According to the method for determining the site of a nuclear power plant based on emergency recommendation provided in the embodiment of the present application, by obtaining the collective effective dose of the proposed site in the target area, the source item unit power of the preset normalized source item, the site unit power of the proposed site and the target core damage frequency, the emergency risk index value of the proposed site can be determined according to the collective effective dose, the source item unit power, the site unit power and the target core damage frequency. In the embodiment of the present application, since the source item unit power, the site unit power and the target core damage frequency can reflect the impact of the safety characteristics of the reactor itself on the site emergency, the emergency risk index value of the proposed site determined by the collective effective dose, the source item unit power, the site unit power and the target core damage frequency can reflect the impact of the safety characteristics of the reactor itself on the site emergency while quantitatively analyzing the emergency feasibility of the proposed site of the nuclear power plant, thereby improving the accuracy of the emergency risk index value of the proposed site, that is, improving the accuracy of the emergency feasibility analysis of the proposed site of the nuclear power plant, thereby improving the accuracy of the determination of the site of the nuclear power plant.

[0161] The specific implementation methods of the above steps are introduced below.

[0162] For the specific implementation of step S310, please refer to the relevant content in Example 1, which will not be repeated here.

[0163] It should be noted that the value of p can be set according to actual conditions and is not limited here. For example, the value of p is 292. Exemplarily, p can be the number of nuclear power plant sites around the world.

[0164] In step S320, the nuclear power plant site may be a proposed site with better emergency conditions.

[0165] It should be noted that the value of q can be set according to actual conditions and is not limited here. For example, the value of q can be 1, 3, 5, 10, etc.

[0166] In some embodiments, determining q nuclear power plant sites from p proposed sites according to p emergency risk indicator values ​​may include:

[0167] For each of the p proposed plant sites, determine the relative risk ranking of the emergency risk index value corresponding to the proposed plant site in all the emergency risk index values ​​to obtain p relative risk rankings;

[0168] In the case where p relative risk rankings are ranked from large to small according to the emergency risk index values, the q proposed sites corresponding to the last q emergency risk index values ​​in the p relative risk rankings are determined as the q nuclear power plant sites;

[0169] When p relative risk rankings are ranked from small to large according to the emergency risk index values, q proposed sites corresponding to the first q emergency risk index values ​​in the p relative risk rankings are determined as q nuclear power plant sites.

[0170] In this embodiment, by ranking the proposed sites according to the emergency risk index values, q nuclear power plant sites can be intuitively determined.

[0171] For example, taking p as 2, q as 1, the emergency risk index value of the proposed site in Taohuajiang as 5.29 man·Sv / reactor-year, and the emergency risk index value of the proposed site in Longyou as 2.73 man·Sv / reactor-year, the proposed site in Longyou is determined as the site of the nuclear power plant.

[0172] In other embodiments, determining q nuclear power plant sites from p proposed sites according to p emergency risk indicator values ​​may include:

[0173] The nuclear power plant sites around the world are respectively used as the proposed sites, and the global emergency risk index value corresponding to each nuclear power plant site in the nuclear power plant sites around the world is determined according to the method for determining the emergency risk index value in Example 1;

[0174] For each of the p emergency risk index values, determine its ranking among all global emergency risk index values, and use the ranking as the risk ranking of the corresponding proposed plant site to obtain p risk rankings;

[0175] When the global emergency risk index values ​​are ranked in descending order, the q proposed sites corresponding to the last q emergency risk index values ​​in the p risk rankings are determined as the q nuclear power plant sites;

[0176] When the global emergency risk index values ​​are ranked in ascending order, the q proposed sites corresponding to the first q emergency risk index values ​​in the p risk rankings are determined as the q nuclear power plant sites.

[0177] For example, taking p as 2, i.e., 2 proposed sites, 292 nuclear power plants worldwide, and q as 1, i.e., 1 nuclear power plant site, as an example, the emergency risk index values ​​within 50km range (i.e., target area) of the 292 nuclear power plants worldwide are calculated, and the segmented statistical results of the emergency risk index values ​​are as follows: Figure 4 shown. Figure 4 The horizontal axis represents the emergency risk index value, and the vertical axis represents the number of proposed plant sites. Figure 4It can be seen that the number of proposed sites with emergency risk index values ​​in the range of 0-1 is 124, accounting for 42% of the total number of sites. For the proposed site of Taohuajiang, its emergency risk index value (5.29 people·Sv / reactor-year) ranks 227th among global sites; for the proposed site of Longyou, its emergency risk index value (2.73 people·Sv / reactor-year) ranks 177th among global sites. It can be seen that considering the influence of population distribution at the site, atmospheric dispersion conditions and the safety characteristics of the reactor itself, from the perspective of emergency feasibility analysis, the proposed site of Longyou is better than the proposed site of Taohuajiang. Therefore, the proposed site of Longyou is determined as the site of the nuclear power plant.

[0178] In order to better understand the method for determining the site of a nuclear power plant based on emergency recommendation provided in an embodiment of the present application, a specific embodiment is described below.

[0179] like Figure 5 As shown, the method for determining the site of a nuclear power plant based on emergency recommendation provided in an embodiment of the present application may include steps S510 to S590.

[0180] S510. Obtain population distribution data.

[0181] S520, determining the population distribution characteristics P(n, j) (i.e., the population quantity P(r, j)) according to the population distribution data;

[0182] S530. Obtain meteorological data (ie, atmospheric dispersion factor) / dose conversion factor.

[0183] S540. Determine the collective effective dose D based on the population distribution data and the site population distribution characteristics P(n, j) T .

[0184] S550. Obtain CDF / unit power (i.e., source unit power and site unit power) / risk conversion factor (i.e., target core damage frequency).

[0185] S560. Determine the weighted collective effective dose D based on CDF / unit power / risk conversion factor. TW (i.e. emergency risk index value).

[0186] S570, according to the weighted collective effective dose D TW , determine the emergency risk index D of the proposed site (i.e. the proposed site) TW (r n ).

[0187] S580, based on the emergency risk index D of the proposed site TW (r n ) to determine the relative emergency risk ranking (i.e. relative risk ranking) of the proposed plant sites.

[0188] S590. Based on the relative emergency risk ranking of the proposed sites, recommend the best site (i.e. the nuclear power plant site).

[0189] In the embodiment of the present application, based on the method for determining the site of a nuclear power plant recommended for emergency, that is, a method for quantitatively evaluating the emergency conditions of a nuclear power plant site based on risk, the collective dose obtained by using the core damage frequency (i.e., the target core damage frequency) and the unit power (i.e., the source unit power and the site unit power) as weight factors is used as the weighted collective dose (i.e., the emergency risk index value) to characterize the risk status of the nuclear power plant. By comparing the emergency risk levels of the proposed site, the relative risk of the proposed site is given, and the emergency conditions of the proposed site are quantitatively evaluated.

[0190] Based on the same inventive concept, an embodiment of the present application also provides an emergency risk indicator determination device. The emergency risk indicator determination device provided in the embodiment of the present application is described below in conjunction with the accompanying drawings.

[0191] Example 3

[0192] like Figure 6 As shown, the emergency risk index value determination device 600 provided in the embodiment of the present application may include a first acquisition module 610 and a first determination module 620.

[0193] The first acquisition module 610 is used to obtain the collective effective dose of the proposed site in the target area, the source item unit power of the preset normalized source item, the site unit power of the proposed site and the target core damage frequency;

[0194] The first determination module 620 is used to determine the emergency risk index value of the proposed site according to the collective effective dose, source term unit power, site unit power and target core damage frequency.

[0195] According to the emergency risk index value determination device provided in the embodiment of the present application, by obtaining the collective effective dose of the proposed site in the target area, the source item unit power of the preset normalized source item, the site unit power of the proposed site and the target core damage frequency, the emergency risk index value of the proposed site can be determined according to the collective effective dose, the source item unit power, the site unit power and the target core damage frequency. In the embodiment of the present application, since the source item unit power, the site unit power and the target core damage frequency can reflect the impact of the safety characteristics of the reactor itself on the site emergency, the emergency risk index value of the proposed site determined by the collective effective dose, the source item unit power, the site unit power and the target core damage frequency can reflect the impact of the safety characteristics of the reactor itself on the site emergency while quantitatively analyzing the emergency feasibility of the proposed site of the nuclear power plant, thereby improving the accuracy of the emergency risk index value of the proposed site, that is, improving the accuracy of the emergency feasibility analysis of the proposed site of the nuclear power plant, thereby improving the accuracy of the determination of the nuclear power plant site.

[0196] In some implementations, the first acquisition module 610 is specifically configured to:

[0197] Obtain n*m sub-areas of the target area, preset normalized source terms, respiratory rate and dose conversion factor, where n and m are both positive integers greater than or equal to 1;

[0198] For each of the n*m ​​sub-areas, obtain the population number and atmospheric diffusion factor corresponding to the sub-area to obtain n*m population numbers and n*m atmospheric diffusion factors;

[0199] The collective effective dose of the proposed site in the target area is determined based on the preset normalized source terms, breathing rate and dose conversion factors, n*m population numbers and n*m atmospheric dispersion factors.

[0200] In some implementations, the first acquisition module 610 is specifically configured to:

[0201] Divide the target area into n*m sub-areas according to n preset radial distances and m radial directions;

[0202] And / or, the first acquisition module 610 is specifically configured to:

[0203] The respiration rate is obtained from the Technical Specification for Environmental Impact Assessment of Release of Airborne Radioactive Materials in Accident Conditions of Nuclear Power Plants NB / T 20182-2012;

[0204] And / or, the first acquisition module 610 is specifically used to: obtain a dose conversion factor from the basic standard for ionizing radiation protection and radiation source safety GB18871;

[0205] And / or, the first acquisition module 610 is specifically configured to:

[0206] The Gaussian plume model is used to determine the atmospheric dispersion factor corresponding to the sub-area.

[0207] In some implementations, the first acquisition module 610 is specifically configured to:

[0208] Determine the collective effective dose of the proposed site in the target area based on the preset normalized source term, breathing rate and dose conversion factor, n*m population and n*m atmospheric dispersion factors, including:

[0209] Substitute the preset normalized source term, breathing rate and dose conversion factor, n*m population and n*m atmospheric dispersion factors into formula (1) to calculate the collective effective dose of the proposed site in the target area;

[0210] Formula (1) includes:

[0211]

[0212] Among them, D T It represents the collective effective dose of the proposed site within the target area; It represents the atmospheric diffusion factor of the sub-area corresponding to the j-th radial direction at the r-th preset radial distance; Q represents the preset normalized source term; BR represents the breathing rate; DFI represents the dose conversion factor; P(r,j) represents the population size of the sub-area corresponding to the j-th radial direction at the r-th preset radial distance; 1≤r≤n, 1≤j≤m.

[0213] In some implementations, the first acquisition module 610 is specifically configured to:

[0214] According to the first-level probabilistic safety analysis of the nuclear power plant, the target core damage frequency is determined.

[0215] In some implementations, the first determining module 620 is specifically configured to:

[0216] Substitute the collective effective dose, source unit power, site unit power and target core damage frequency into formula (2) to calculate the emergency risk index value of the proposed site;

[0217] Formula (2) includes:

[0218]

[0219] Among them, D TW Indicates the emergency risk index value of the proposed site; D T W represents the collective effective dose of the proposed site in the target area; s Indicates source unit power; W rrepresents the unit power at the site; CDF represents the target core damage frequency.

[0220] The emergency risk index value determination device provided in the embodiment of the present application can be used to execute the emergency risk index value determination method, that is, it has the beneficial effects and implementation methods of the emergency risk index value determination method provided in Example 1 of the present application. For details, please refer to the specific description of the emergency risk index value determination method in the above Example 1, and this embodiment will not be repeated here.

[0221] Example 4

[0222] Based on the same inventive concept, an embodiment of the present application also provides a system for determining a nuclear power plant site based on emergency recommendation. The system for determining a nuclear power plant site based on emergency recommendation provided by an embodiment of the present application is described below in conjunction with the accompanying drawings.

[0223] like Figure 7 As shown, the nuclear power plant site determination system 100 based on emergency recommendation provided in the embodiment of the present application includes the emergency risk index value determination device 600 and the nuclear power plant site determination device 700 of any one of the embodiments 3.

[0224] The emergency risk index value determination device 600 is used to determine p emergency risk index values ​​corresponding to p proposed factory sites, where p is a positive integer;

[0225] The nuclear power plant site determination device 700 is connected to the emergency risk index value determination device 600, and is used to determine q nuclear power plant sites from p proposed sites according to p emergency risk index values, 1≤q≤p.

[0226] According to the system for determining the site of a nuclear power plant based on emergency recommendation provided by the embodiment of the present application, by obtaining the collective effective dose of the proposed site in the target area, the source item unit power of the preset normalized source item, the site unit power of the proposed site and the target core damage frequency, the emergency risk index value of the proposed site can be determined according to the collective effective dose, the source item unit power, the site unit power and the target core damage frequency. In the embodiment of the present application, since the source item unit power, the site unit power and the target core damage frequency can reflect the impact of the safety characteristics of the reactor itself on the site emergency, the emergency risk index value of the proposed site determined by the collective effective dose, the source item unit power, the site unit power and the target core damage frequency can reflect the impact of the safety characteristics of the reactor itself on the site emergency while quantitatively analyzing the emergency feasibility of the proposed site of the nuclear power plant, thereby improving the accuracy of the emergency risk index value of the proposed site, that is, improving the accuracy of the emergency feasibility analysis of the proposed site of the nuclear power plant, thereby improving the accuracy of the determination of the site of the nuclear power plant.

[0227] In some implementations, the nuclear power plant site determination device 700 is specifically used to:

[0228] For each of the p proposed plant sites, determine the relative risk ranking of the emergency risk index value corresponding to the proposed plant site in all the emergency risk index values ​​to obtain p relative risk rankings;

[0229] In the case where p relative risk rankings are ranked from large to small according to the emergency risk index values, the q proposed sites corresponding to the last q emergency risk index values ​​in the p relative risk rankings are determined as the q nuclear power plant sites;

[0230] When p relative risk rankings are ranked from small to large according to the emergency risk index values, q proposed sites corresponding to the first q emergency risk index values ​​in the p relative risk rankings are determined as q nuclear power plant sites.

[0231] The system for determining the site of a nuclear power plant based on emergency recommendation provided in the embodiment of the present application can be used to execute the method for determining the site of a nuclear power plant based on emergency recommendation, that is, it has the beneficial effects and implementation methods of the method for determining the site of a nuclear power plant based on emergency recommendation provided in Example 2 of the present application. For details, please refer to the specific description of the method for determining the site of a nuclear power plant based on emergency recommendation in the above Example 2, which will not be repeated in this embodiment.

[0232] It is to be understood that the above embodiments are merely exemplary embodiments used to illustrate the principles of the present application, but the present application is not limited thereto. For those skilled in the art, various modifications and improvements can be made without departing from the spirit and substance of the present application, and these modifications and improvements are also considered to be within the scope of protection of the present application.

Claims

1. A method for determining an emergency risk index value, characterized in that: include: Obtain the collective effective dose of the proposed site in the target area, the source unit power of the preset normalized source term, the site unit power of the proposed site and the target core damage frequency; The emergency risk index value of the proposed site is determined based on the collective effective dose, the source-term unit power, the site unit power and the target core damage frequency.

2. The method according to claim 1, characterized in that Obtain the collective effective dose of the proposed site within the target area, including: Obtain n*m sub-areas of the target area, preset normalized source terms, respiratory rate and dose conversion factor, where n and m are both positive integers greater than or equal to 1; For each of the n*m ​​sub-areas, obtain the population number and atmospheric diffusion factor corresponding to the sub-area to obtain n*m population numbers and n*m atmospheric diffusion factors; The collective effective dose of the proposed site in the target area is determined based on the preset normalized source terms, breathing rate and dose conversion factors, n*m population numbers and n*m atmospheric dispersion factors.

3. The method according to claim 2, characterized in that Get n*m sub-areas of the target area, including: Divide the target area into n*m sub-areas according to n preset radial distances and m radial directions; and / or, obtain respiration rate, including: The respiration rate is obtained from the Technical Specification for Environmental Impact Assessment of Release of Airborne Radioactive Materials in Accident Conditions of Nuclear Power Plants NB / T 20182-2012; and / or, obtain dose conversion factors, including: Get the dose conversion factor from the basic standard for ionizing radiation protection and radiation source safety GB18871; And / or, obtain the atmospheric dispersion factor corresponding to the sub-area, including: The Gaussian plume model is used to determine the atmospheric dispersion factor corresponding to the sub-area.

4. The method according to claim 2, characterized in that: The collective effective dose of the proposed site in the target area is determined based on the preset normalized source term, breathing rate and dose conversion factor, n*m population numbers and n*m atmospheric dispersion factors, including: Substitute the preset normalized source term, breathing rate and dose conversion factor, n*m population and n*m atmospheric dispersion factors into formula (1) to calculate the collective effective dose of the proposed site in the target area; The formula (1) includes: Among them, D T It represents the collective effective dose of the proposed site within the target area; It represents the atmospheric diffusion factor of the sub-area corresponding to the j-th radial direction at the r-th preset radial distance; Q represents the preset normalized source term; BR represents the breathing rate; DFI represents the dose conversion factor; P(r,j) represents the population size of the sub-area corresponding to the j-th radial direction at the r-th preset radial distance; 1≤r≤n, 1≤j≤m.

5. The method according to any one of claims 1 to 4, characterized in that Obtain target core damage frequency, including: According to the first-level probabilistic safety analysis of the nuclear power plant, the target core damage frequency is determined.

6. The method according to any one of claims 1 to 4, characterized in that Determining the emergency risk index value of the proposed site according to the collective effective dose, the source unit power, the site unit power and the target core damage frequency includes: Substituting the collective effective dose, the source unit power, the site unit power and the target core damage frequency into formula (2) for calculation, the emergency risk index value of the proposed site is obtained; The formula (2) includes: Among them, D TW Indicates the emergency risk index value of the proposed site; D T W represents the collective effective dose of the proposed site in the target area; s Indicates source unit power; W r represents the unit power at the site; CDF represents the target core damage frequency.

7. A method for determining the site of a nuclear power plant based on emergency recommendation, characterized in that: include: According to the method for determining emergency risk index values ​​according to any one of claims 1 to 6, p emergency risk index values ​​corresponding to p proposed plant sites are determined, where p is a positive integer; According to p emergency risk index values, q nuclear power plant sites are determined from p proposed sites, 1≤q≤p.

8. The method according to claim 7, characterized in that The step of determining q nuclear power plant sites from p proposed sites based on p emergency risk index values ​​includes: For each of the p proposed plant sites, determine the relative risk ranking of the emergency risk index value corresponding to the proposed plant site among all the emergency risk index values ​​to obtain p relative risk rankings; In the case where p relative risk rankings are ranked from large to small according to the emergency risk index values, the q proposed sites corresponding to the last q emergency risk index values ​​in the p relative risk rankings are determined as the q nuclear power plant sites; When p relative risk rankings are ranked from small to large according to the emergency risk index values, q proposed sites corresponding to the first q emergency risk index values ​​in the p relative risk rankings are determined as q nuclear power plant sites.

9. A device for determining an emergency risk index value, characterized in that: include: The first acquisition module is used to obtain the collective effective dose of the proposed site in the target area, the source item unit power of the preset normalized source item, the site unit power of the proposed site and the target core damage frequency; The first determination module is used to determine the emergency risk index value of the proposed site according to the collective effective dose, the source unit power, the site unit power and the target core damage frequency.

10. The device according to claim 9, characterized in that The first acquisition module is specifically used for: Obtain n*m sub-areas of the target area, preset normalized source terms, respiratory rate and dose conversion factor, where n and m are both positive integers greater than or equal to 1; For each of the n*m ​​sub-areas, obtain the population number and atmospheric diffusion factor corresponding to the sub-area to obtain n*m population numbers and n*m atmospheric diffusion factors; The collective effective dose of the proposed site in the target area is determined based on the preset normalized source terms, breathing rate and dose conversion factors, n*m population numbers and n*m atmospheric dispersion factors.

11. The device according to claim 10, characterized in that The first acquisition module is specifically used to: Substitute the preset normalized source term, breathing rate and dose conversion factor, n*m population and n*m atmospheric dispersion factors into formula (1) to calculate the collective effective dose of the proposed site in the target area; The formula (1) includes: Among them, D T It represents the collective effective dose of the proposed site within the target area; It represents the atmospheric diffusion factor of the sub-area corresponding to the j-th radial direction at the r-th preset radial distance; Q represents the preset normalized source term; BR represents the breathing rate; DFI represents the dose conversion factor; P(r,j) represents the population size of the sub-area corresponding to the j-th radial direction at the r-th preset radial distance; 1≤r≤n, 1≤j≤m.

12. The device according to claim 9, characterized in that The first determination module is specifically used for: Substituting the collective effective dose, the source unit power, the site unit power and the target core damage frequency into formula (2) for calculation, the emergency risk index value of the proposed site is obtained; The formula (2) includes: Among them, D TW Indicates the emergency risk index value of the proposed site; D T W represents the collective effective dose of the proposed site in the target area; s Indicates source unit power; W r represents the unit power at the site; CDF represents the target core damage frequency.

13. A system for determining the site of a nuclear power plant based on emergency recommendation, characterized in that: include: The device for determining an emergency risk index value according to any one of claims 9 to 12, used to determine p emergency risk index values ​​corresponding to p proposed plant sites, where p is a positive integer; The nuclear power plant site determination device is connected to the emergency risk index value determination device and is used to determine q nuclear power plant sites from p proposed sites according to p emergency risk index values, 1≤q≤p.

14. The system according to claim 13, characterized in that The nuclear power plant site determination device is specifically used for: For each of the p proposed plant sites, determine the relative risk ranking of the emergency risk index value corresponding to the proposed plant site among all the emergency risk index values ​​to obtain p relative risk rankings; In the case where p relative risk rankings are ranked from large to small according to the emergency risk index values, the q proposed sites corresponding to the last q emergency risk index values ​​in the p relative risk rankings are determined as the q nuclear power plant sites; When p relative risk rankings are ranked from small to large according to the emergency risk index values, q proposed sites corresponding to the first q emergency risk index values ​​in the p relative risk rankings are determined as q nuclear power plant sites.

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