Dose evaluation method for special public near nuclear facility
Through a dose evaluation method for special publics near nuclear facilities, the problem of failure to fully evaluate special public radiation doses in the prior art is solved, and more accurate assessment and control of the impact of radiation near nuclear facilities is achieved, and scientific basis is provided for radiation protection and health risk management.
Patent Information
- Application Number
- CN202411859765.0
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2024-12-17
- Publication Date
- 2025-05-16
AI Technical Summary
The prior art has failed to fully consider the differences in residence locations, residence times and pathways for the special public around nuclear facilities, and has failed to effectively evaluate their radiation dose, especially the impact of nuclear lining in surface soils over the year-on-year accumulation and key radiation pathways.
A special public dose evaluation method is proposed for the near nuclear facilities. By collecting radioactive dose evaluation parameter data of target special publics, using environmental quality assessment model to estimate the distribution of radionuclide concentration, calculating the individual's annual effective dose, and comparative analysis is performed based on GB 18871 and the preset threshold value of the public dose constraint value of the nuclear facilities.
This method can more accurately assess the radiation impact of special publics, meet the radiation impact control level near nuclear facilities, and provide scientific basis for special publics to radiation protection and health risk management.
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Figure CN120012351A_ABST
Abstract
Description
Technical Field
[0001] The invention relates to the technical field of radiation protection and environmental safety, and in particular to a special public dose assessment method used near nuclear facilities. Background Art
[0002] As a clean and efficient energy source, nuclear energy has been widely developed around the world in recent years. However, the development of nuclear energy is also accompanied by the potential impact of radioactive radiation on the environment and people. How to ensure the sustainable development of nuclear energy under the premise of safety has become one of the main problems facing the development of nuclear energy.
[0003] The primary condition for ensuring nuclear energy safety is to truly characterize the radiation doses of different exposed groups during the operation of nuclear facilities and to propose effective measures to reduce the exposure doses from the perspective of radiation protection. In the research on radiation dose assessment of nuclear facility operation at home and abroad, the focus is mainly on the radiation dose assessment of occupational exposed personnel, the general public, and the medical exposure population. Existing technologies have established relatively complete assessment methods for the radiation doses of these groups under nuclear facility accidents and normal operating conditions. However, for the special public around nuclear facilities, such as workers in working enterprises around nuclear facilities, armed police soldiers, and temporary personnel working in nuclear facilities, there are few studies on the radiation dose assessment of these groups, and the relevant assessment methods are still imperfect.
[0004] Especially in the site selection stage of nuclear facilities, this type of special public usually does not exist or is not considered. However, in the actual operation of nuclear facilities, these special public become the group with higher risk of exposure due to their close distance to nuclear facilities and special nature of work. Especially in the retrospective evaluation and in-process supervision of nuclear facility operation, the exposure dose of this group of people has become the focus of radiation protection. However, the current assessment methods for the exposure dose of these special public still have the following deficiencies: they fail to fully consider the differences between their residence location, residence time and exposure pathways and those of the general public; they fail to pay enough attention to some key radiation pathways (such as inhalation internal exposure due to resuspension of nuclides in the soil and external exposure due to air immersion); and they fail to reflect the impact of the annual accumulation of nuclides in the surface soil.
[0005] In view of the above problems, the present invention is proposed. Summary of the invention
[0006] The invention discloses a special public dose assessment method for the vicinity of a nuclear facility, aiming to solve the technical problems existing in the prior art.
[0007] The present invention provides a special public dose assessment method for use near nuclear facilities, comprising:
[0008] Collect radiation dose assessment parameter data for target special publics;
[0009] Use environmental quality assessment models to estimate the distribution of radionuclide concentrations in the air, surface soil, and biological media near nuclear facilities;
[0010] Calculate the individual annual effective dose. During the period when the target special public reside in different locations at the boundary of the nuclear facility, the calculation of the individual annual effective dose includes the inhalation internal exposure dose, air immersion external exposure dose, and surface deposition external exposure dose of the target special public; during the period when the target special public resides in the living area, the calculation of the individual annual effective dose includes the inhalation internal exposure dose, air immersion external exposure dose, surface deposition external exposure dose, and ingestion internal exposure dose;
[0011] Taking GB 18871 and the public dose constraint value of nuclear facilities as the preset threshold, the individual annual effective dose is compared and analyzed with the preset threshold:
[0012] If the preset threshold requirements are met, the radiation impact control level near the nuclear facility is met;
[0013] If the preset threshold requirements are not met, the radiation impact control level near the nuclear facility is not met.
[0014] As a preferred technical solution, the calculation of the inhalation internal radiation dose is based on the concentration of radionuclide i in the indoor and outdoor air using the following formula:
[0015]
[0016] Where:
[0017] C airi外 is the concentration of radionuclide i in outdoor air at location j, Bq / m 3 ;
[0018] C re is the concentration in ambient air due to the resuspension of radionuclide i in outdoor air at location j, Bq / m 3 ;
[0019] C rei =K i ×C gi
[0020] K i is the resuspension factor of radionuclide i, / m;
[0021] C gi is the cumulative fallout of radionuclides per unit area, Bq / m 2 ;
[0022] C airj内 is the concentration of radionuclide i in the indoor air at location j, Bq / m 3 ;
[0023] DCF inhi is the inhalation internal radiation dose conversion factor of radionuclide i, Sv / Bq;
[0024] R a外 The annual outdoor air intake of the target special public, m 3 / a;
[0025] R a内 The annual indoor air intake of the target special public, m 3 / a.
[0026] As a preferred technical solution, the calculation of air immersion external radiation dose is based on the concentration of radionuclide i in the indoor and outdoor air using the following formula:
[0027]
[0028] Where:
[0029] DCF imj is the effective dose conversion factor of radionuclide i to human body immersed in semi-infinite smoke cloud, (Sv / h) / (Bq / m 3 ).
[0030] As a preferred technical solution, the calculation of surface deposition external radiation dose is based on the concentration of radionuclide i in the indoor and outdoor air using the following formula:
[0031]
[0032] Where:
[0033] DCF gi is the effective dose conversion factor of radionuclide i in sediment to human body, (Sv / h) / (Bq / m 2 );
[0034] C gi is the surface cumulative deposition of radionuclide i at the calculation point, Bq / m 2 .
[0035] As a preferred technical solution, C gi The calculation takes into account the impact of the cumulative amount changing year by year, and uses the following formula:
[0036]
[0037] Where:
[0038] C gi (n) represents the cumulative amount of radionuclide i deposited on the ground per unit area in time period n, Bq / m 2 ;
[0039] i represents the nuclide category;
[0040] λ i Represents the decay constant of radionuclide i, / d or / s or / a;
[0041] R rei It indicates the amount of radioactive nuclide i in the soil per unit area that is resuspended and enters the ambient air, Bq / m 2 ;
[0042]
[0043] Where:
[0044] χ i is the dilution factor of pollutants in the air, s / m 3 .
[0045] R di It indicates the amount of radioactive nuclide i in the soil per unit area that penetrates into the groundwater environment, Bq / m 2 ;
[0046]
[0047] Where:
[0048] L i represents the rate of penetration of radionuclide i into the underlying soil, m / s;
[0049] d represents the thickness of the topsoil.
[0050] As a preferred technical solution, the thickness of the surface soil is 15cm-30cm.
[0051] As a preferred technical solution, the calculation of the internal radiation dose by ingestion adopts the following formula:
[0052]
[0053] Where:
[0054] DCF ingi The effective dose conversion factor of ingested radionuclide i to human body, Sv / Bq;
[0055] U ingi For the special public individuals who ingest the 3 H and 14 The amount of radionuclide i other than C, Bq / a.
[0056] As a preferred technical solution, U ingi The calculation takes into account the different types of consumer goods and adopts the following formula:
[0057]
[0058] Where:
[0059] U r Rice consumption of target special public individuals, kg / a;
[0060] U f The surface consumption of target special public individuals, kg / a;
[0061] U o The consumption of other potatoes and beans by the target special public individuals, kg / a;
[0062] U lv Leafy vegetable consumption of target special public individuals, kg / a;
[0063] U rv The consumption of root vegetables by the target special public individuals, kg / a;
[0064] U fv The consumption of fruit and vegetables by target special public individuals, kg / a;
[0065] U av Aquatic vegetable consumption of target special public individuals, kg / a;
[0066] U p The pork consumption of the target special public individuals, kg / a;
[0067] U m The mutton consumption of the target special public individuals, kg / a;
[0068] U b The beef consumption of the target special public individuals, kg / a;
[0069] U q The poultry meat consumption of the target special public individuals, kg / a;
[0070] U y Fish consumption of target specific public individuals, kg / a;
[0071] U e The egg consumption of the target special public individuals, kg / a;
[0072] U m Milk consumption of target special public individuals, kg / a;
[0073] U s The fruit consumption of target special public individuals, kg / a;
[0074] U w The drinking water consumption of the target special public individuals, kg / a;
[0075] U t The amount of soil accidentally ingested by the target special public individuals, kg / a;
[0076] C xi is the concentration of radionuclide i in X-type food and other items, Bq / kg or Bq / L, X is a subscript representing different types of food and other objects, the same as consumption;
[0077] F x The share of food and other items of category X originating from the evaluation area;
[0078] t r ,t f ,t o is the time interval from harvest to consumption of rice, noodles and other crops, d;
[0079] t lv ,t rv ,t fv ,t av The time interval from harvesting to consumption of leafy, root, tuber, fruit, and aquatic vegetables is d;
[0080] t p ,t m ,t b ,t q is the time interval from the slaughter of meat-producing animals to their consumption, d;
[0081] t m is the time interval from milking to milk consumption, d;
[0082] t e is the time interval from egg laying / collecting to egg consumption, d;
[0083] r is the processing factor (translocation factor).
[0084] As a preferred technical solution, the radiation dose assessment parameter data of the target special public is collected, including:
[0085] Nuclear facility effluent emission data, emission source characteristic data, meteorological parameters, population distribution, target special public food consumption data (food source and intake data), target special public living habits (residence factor setting), working conditions and intensity parameters (for subsequent breathing rate selection), dose conversion factors, and bioconcentration parameters.
[0086] The technical solution adopted by the present invention can achieve at least one of the following beneficial effects:
[0087] 1. The present invention collects specific parameters of the target special public, such as the residence location, living habits, food consumption, etc., and combines the nuclear facility emission source items and environmental distribution model to accurately assess the impact of radionuclides in the air, soil and biological media on specific populations, which is more targeted and applicable. This method provides a scientific basis for radiation protection of special publics and meets the needs of public health risk management near nuclear facilities.
[0088] 2. The present invention includes the internal radiation dose caused by the ingestion of radionuclides deposited on the surface and re-suspension into the ambient atmosphere to the target public into the assessment scope. By refining the re-suspension factor and the migration behavior of nuclides in the environment, the complex interaction between air, soil and food chain is fully considered, making the assessment results more in line with the actual situation and improving the early warning ability and scientificity of long-term radiation risks.
[0089] 3. This invention introduces a dynamic calculation method for the annual changes in the accumulation of radionuclides deposited on the surface, which fully considers the comprehensive influence of factors such as nuclide decay, resuspension and infiltration into groundwater. Compared with the traditional static calculation method, this method can more truly reflect the long-term changes in environmental radiation, provide important support for the accurate prediction of external radiation dose, and improve the practicality and foresight of the evaluation method.
[0090] 4. The present invention refines the radiation dose assessment of the target special public into different residence locations (nuclear facility boundaries and living areas) and indoor and outdoor environments, and combines multi-path calculations of inhaled internal exposure, air immersion external exposure, surface deposition external exposure and ingested internal exposure, making the results more accurate and comprehensive. At the same time, through the detailed analysis of food consumption classification and time intervals, the present invention further improves the accuracy of ingested internal exposure dose assessment, and provides comprehensive technical support for public dose monitoring and risk management around nuclear facilities. BRIEF DESCRIPTION OF THE DRAWINGS
[0091] In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the following briefly introduces the drawings required for describing the embodiments, which constitute a part of the present invention. The exemplary embodiments of the present invention and their descriptions explain the present invention and do not constitute improper limitations on the present invention. In the drawings:
[0092] Figure 1 The figure is a flow chart of a special public dose assessment method for use near nuclear facilities according to the present invention. DETAILED DESCRIPTION
[0093] In order to make the purpose, technical solution and advantages of the present invention clearer, the technical solution of the present invention will be clearly and completely described below in conjunction with the specific embodiments of the present invention and the corresponding drawings. In the description of the present invention, it should be noted that the term "or" is usually used in the sense of including "and / or", unless the content clearly indicates otherwise.
[0094] In the description of the present invention, it should be noted that, unless otherwise clearly specified and limited, the terms "installed", "connected" and "connected" should be understood in a broad sense. For example, it can be a fixed connection, a detachable connection, or an integral connection; it can be a mechanical connection or a magnetic connection; it can be a direct connection, or it can be indirectly connected through an intermediate medium, or it can be internal communication between two elements. For ordinary technicians in this field, the specific meanings of the above terms in the present invention can be understood according to specific circumstances. In addition, in the description of this application, the terms "first", "second", etc. are only used to distinguish the description and cannot be understood as indicating or implying relative importance.
[0095] Obviously, the described embodiments are only some embodiments of the present invention, not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by ordinary technicians in this field without creative work are within the scope of protection of the present invention.
[0096] First, in order to facilitate understanding of the embodiments of the present invention, some terms or nouns involved in the present invention are explained below:
[0097] Target special public refers to employees of other industrial and mining enterprises around or near nuclear facilities and managers of nuclear facility imports and exports. The target special public stays at different locations on the nuclear facility boundary for 8 hours per day and in living areas for 16 hours per day.
[0098] Internal exposure due to inhalation refers to the radiation exposure caused by inhalation of radioactive substances through the respiratory tract. The exposure pathways are divided into two types: indoor and outdoor.
[0099] Air immersion external radiation refers to the radiation dose generated when a person is placed in an air environment containing radioactive gases or aerosols. These radioactive substances directly irradiate the outside of the human body. The exposure pathways are divided into indoor and outdoor.
[0100] External radiation from surface deposition refers to the radiation dose received by the human body caused by radioactive materials deposited on the surface of the earth and then transmitted through the air to the outside of the human body. The exposure pathways are divided into two types: indoor and outdoor.
[0101] Internal exposure through ingestion refers to internal exposure caused by ingesting terrestrial food, aquatic organisms, drinking water, and accidentally ingesting soil. The radiation dose depends on personal eating habits and the degree of food contamination.
[0102] To solve the problems existing in the prior art, an embodiment of the present invention provides a special public dose assessment method for use near nuclear facilities, such as Figure 1 As shown, including:
[0103] Data collection step S1: Collecting radioactive dose assessment parameter data of target special public, including nuclear facility effluent emission data, emission source item characteristic data, meteorological parameters, population distribution, target special public food consumption data (food source and intake data), target special public living habits (residence factor setting), working conditions and intensity parameters (for subsequent respiratory rate selection), dose conversion factors, bioconcentration parameters, etc.;
[0104] Radionuclide concentration distribution assessment step S2: Use mature models such as CairDOS, AERMOD, and REIA to estimate the distribution of radionuclide concentrations in the air, surface soil, and biological media near nuclear facilities;
[0105] Individual annual effective dose calculation step S3: during the period when the target special public reside at different locations at the nuclear facility boundary, the inhalation internal exposure dose, air immersion external exposure dose, and surface deposition external exposure dose of the target special public are calculated respectively; during the period when the target special public reside in the living area, the inhalation internal exposure dose, air immersion external exposure dose, surface deposition external exposure dose, and ingestion internal exposure dose are calculated respectively;
[0106] Inhalation internal radiation dose calculation step S31: Based on the difference in breathing rate of the target special public during outdoor activities and indoor activities, the individual annual inhalation internal radiation dose is calculated using the following formula based on the concentration of radioactive nuclide i in the air indoors and outdoors:
[0107]
[0108] Where:
[0109] C airi外 is the concentration of radionuclide i in outdoor air at location j, Bq / m 3 ;
[0110] C re is the concentration in ambient air due to the resuspension of radionuclide i in outdoor air at location j, Bq / m 3 ;
[0111] C rei =K i ×C gi
[0112] K i is the resuspension factor of radionuclide i, / m;
[0113] C gi is the cumulative fallout of radionuclides per unit area, Bq / m 2 ;
[0114] C airj内 is the concentration of radionuclide i in the indoor air at location j, Bq / m 3 ;
[0115] DCF inhi is the inhalation internal radiation dose conversion factor of radionuclide i, Sv / Bq;
[0116] R a外 The annual outdoor air intake of the target special public, m 3 / a;
[0117] R a内 The annual indoor air intake of the target special public, m 3 / a;
[0118] Among them, taking into account the internal exposure caused by inhalation of resuspended radioactive nuclides i, the above formula takes into account the inhalation internal exposure of the target special public caused by the resuspension of radionuclides deposited on the ground into the atmospheric environment; this design fully considers the possibility of surface pollutants entering the air under specific conditions (such as wind, human disturbance), and can more accurately predict the potential hazards of radionuclides to human health, so as to further improve the calculation results of inhalation internal exposure.
[0119] Air immersion external exposure dose calculation step S32: Considering that the target special public stays indoors and outdoors, the air immersion external exposure dose is slightly different due to the different concentrations in the ambient air. Based on the concentrations of radioactive nuclides i in the air indoors and outdoors, the following formula is used to calculate the exposure dose of the target special public when they stay indoors and when they stay outdoors:
[0120]
[0121] Where:
[0122] DCF imj is the effective dose conversion factor of radionuclide i to human body immersed in semi-infinite smoke cloud, (Sv / h) / (Bq / m 3 );
[0123] Calculation step S33 of external radiation dose of surface deposition: Considering that the target special public stays indoors, the content of radioactive nuclides i on the indoor ground is relatively low due to frequent cleaning, so the external radiation of surface deposition when the public is outdoors is mainly evaluated. At the same time, the calculation method of cumulative amount changing year by year is introduced in the calculation of external radiation of outdoor surface deposition, so as to dynamically reflect the decay law, migration characteristics and long-term influence of changes in environmental conditions on external radiation dose of radioactive nuclides over time; compared with the traditional static calculation method, this design can more accurately evaluate the long-term environmental radiation risk and provide accurate data support for the formulation of scientific and reasonable radioactive pollution protection strategies. The following formula is used for calculation:
[0124]
[0125] Where:
[0126] DCF gi is the effective dose conversion factor of radionuclide i in sediment to human body, (Sv / h) / (Bq / m 2 );
[0127] C gi is the surface cumulative deposition of radionuclide i at the calculation point, Bq / m 2 ;
[0128] Among them, the surface cumulative deposition amount C gi It is obtained in the following way, that is, the amount of radionuclides that settle to the ground each year, minus the amount of nuclides that resuspend and enter the atmosphere, the amount that infiltrates into the soil environment, and the amount of decay, according to the following formula (when the nuclear facility has been in operation for n years):
[0129]
[0130] Where:
[0131] C gi (n) represents the cumulative amount of radionuclide i deposited on the ground per unit area in time period n, Bq / m 2 ;
[0132] i represents the nuclide category;
[0133] λ i Represents the decay constant of radionuclide i, / d or / s or / a;
[0134] R rei It indicates the amount of radioactive nuclide i in the soil per unit area that is resuspended and enters the ambient air, Bq / m 2 ;
[0135]
[0136] Where:
[0137] χ i is the dilution factor of pollutants in the air, s / m 3 .
[0138] R di It indicates the amount of radioactive nuclide i in the soil per unit area that penetrates into the groundwater environment, Bq / m 2 ;
[0139]
[0140] Where:
[0141] L i represents the rate of penetration of radionuclide i into the underlying soil, m / s;
[0142] d represents the thickness of the surface soil, which is generally 15cm-30cm;
[0143] Ingestion internal radiation dose calculation step S34: Combined with the population and environmental survey results around nuclear facilities over the years, consumer goods categories are selected and the ingestion internal radiation dose is calculated using the following formula:
[0144]
[0145] Where:
[0146] DCF ingi The effective dose conversion factor of ingested radionuclide i to human body, Sv / Bq;
[0147] U ingi For the special public individuals who ingest the 3 H and 14 The amount of radionuclide i other than C, Bq / a;
[0148] Preferably, the consumer goods categories are selected from rice (including rice and millet, etc.), noodles, others (mainly potatoes and beans, etc.), leafy vegetables, root vegetables, fruit vegetables, aquatic vegetables, pork, mutton, beef, poultry (including chicken, duck, goose, pigeon and quail, etc.), fish (including freshwater fish, crustaceans, molluscs and algae, etc.), eggs, milk, fruits and drinking water, and the consumption of the above consumer goods categories is combined to calculate U ingi :
[0149]
[0150] Where:
[0151] U r Rice consumption of target special public individuals, kg / a;
[0152] Uf The surface consumption of target special public individuals, kg / a;
[0153] U o The consumption of other potatoes and beans by the target special public individuals, kg / a;
[0154] U lv Leafy vegetable consumption of target special public individuals, kg / a;
[0155] U rv The consumption of root vegetables by the target special public individuals, kg / a;
[0156] U fv The consumption of fruit and vegetables by target special public individuals, kg / a;
[0157] U av Aquatic vegetable consumption of target special public individuals, kg / a;
[0158] U p The pork consumption of the target special public individuals, kg / a;
[0159] U m The mutton consumption of the target special public individuals, kg / a;
[0160] U b The beef consumption of the target special public individuals, kg / a;
[0161] U q The poultry meat consumption of the target special public individuals, kg / a;
[0162] U y Fish consumption of target specific public individuals, kg / a;
[0163] U e The egg consumption of the target special public individuals, kg / a;
[0164] U m Milk consumption of target special public individuals, kg / a;
[0165] U s The fruit consumption of target special public individuals, kg / a;
[0166] U w The drinking water consumption of the target special public individuals, kg / a;
[0167] U t The amount of soil accidentally ingested by the target special public individuals, kg / a;
[0168] Cxi is the concentration of radionuclide i in X-type food and other items, Bq / kg or Bq / L, X is a subscript representing different types of food and other objects, the same as consumption;
[0169] F x The share of food and other items of category X originating from the evaluation area;
[0170] t r ,t f ,t o is the time interval from harvest to consumption of rice, noodles and other crops, d;
[0171] t lv ,t rv ,t fv ,t av The time interval from harvesting to consumption of leafy, root, tuber, fruit, and aquatic vegetables is d;
[0172] t p ,t m ,t b ,t q is the time interval from the slaughter of meat-producing animals to their consumption, d;
[0173] t m is the time interval from milking to milk consumption, d;
[0174] t e is the time interval from egg laying / collecting to egg consumption, d;
[0175] r is the processing factor (translocation factor);
[0176] Individual annual effective dose result judgment step S4: Taking GB 18871 "Basic Standard for Ionizing Radiation Protection and Radiation Source Safety" and the public dose constraint value of nuclear facilities as the preset threshold, the above individual annual effective dose results are compared and analyzed with the preset threshold of the nuclear facility site:
[0177] If the preset threshold requirements are met, the radiation impact control level near the nuclear facility is met;
[0178] If the preset threshold requirements are not met, the radiation impact control level near the nuclear facility is not met.
[0179] The embodiments of the present invention are described above in conjunction with the accompanying drawings, but the present invention is not limited to the above-mentioned specific implementation methods. The above-mentioned specific implementation methods are merely illustrative and not restrictive. Under the enlightenment of the present invention, ordinary technicians in this field can also make many forms without departing from the scope of protection of the present invention and the claims, all of which are within the protection of the present invention.
Claims
1. A special public dose assessment method for use near nuclear facilities, characterized in that: include: Collect radiation dose assessment parameter data for target special publics; Use environmental quality assessment models to estimate the distribution of radionuclide concentrations in the air, surface soil, and biological media near nuclear facilities; Calculate the individual annual effective dose. During the period when the target special public resides at different locations at the boundary of the nuclear facility, the calculation of the individual annual effective dose includes the inhalation internal exposure dose, air immersion external exposure dose, and surface deposition external exposure dose of the target special public; during the period when the target special public resides in the living area, the calculation of the individual annual effective dose includes the inhalation internal exposure dose, air immersion external exposure dose, surface deposition external exposure dose, and ingestion internal exposure dose; Taking GB 18871 and the public dose constraint value of nuclear facilities as the preset threshold, the individual annual effective dose is compared and analyzed with the preset threshold: If the preset threshold requirement is met, the radiation impact control level near the nuclear facility is met; If the preset threshold requirement is not met, the radiation impact control level near the nuclear facility is not met.
2. The special public dose assessment method according to claim 1, characterized in that: The calculation of the inhalation internal radiation dose is based on the concentration of radionuclide i in the indoor and outdoor air using the following formula: Where: C airi外 is the concentration of the radionuclide i in the outdoor air at location j, Bq / m 3 ; C re is the concentration in ambient air due to the resuspension of the radionuclide i in the outdoor air at location j, Bq / m 3 ; C rei =K i ×C gi K i is the resuspension factor of the radionuclide i, / m; C gi is the cumulative fallout of the radionuclide per unit area, Bq / m 2 ; C airj内 is the concentration of the radionuclide i in the indoor air at location j, Bq / m 3 ; DCF inhi is the inhalation internal radiation dose conversion factor of the radionuclide i, Sv / Bq; R a外 Annual outdoor air intake of the target special public, m 3 / a; R a内 The annual indoor air intake of the target special public, m 3 / a.
3. The special public dose assessment method according to claim 1, characterized in that: The calculation of the air immersion external radiation dose is based on the concentration of the radionuclide i in the indoor and outdoor air using the following formula: Where: DCF imj is the effective dose conversion factor of the radionuclide i to the human body immersed in a semi-infinite cloud, (Sv / h) / (Bq / m 3 ).
4. The special public dose assessment method according to claim 1, characterized in that: The calculation of the surface deposition external radiation dose is based on the concentration of the radionuclide i in the indoor and outdoor air using the following formula: Where: DCF gi is the effective dose conversion factor of the radionuclide i in the sediment to the human body, (Sv / h) / (Bq / m 2 ); C gi is the cumulative surface deposition of the radionuclide i at the calculation point, Bq / m 2 .
5. The special public dose assessment method according to claim 4, characterized in that: The C gi The calculation takes into account the impact of the cumulative amount changing year by year, and uses the following formula: Where: C gi (n) represents the cumulative amount of the radionuclide i deposited on the ground per unit area in time period n, Bq / m 2 ; i represents the nuclide category; λ i represents the decay constant of the radionuclide i, / d or / s or / a; R rei It indicates the amount of radioactive nuclide i in the soil per unit area that is resuspended and enters the ambient air, Bq / m 2 ; Where: χ i is the dilution factor of pollutants in the air, s / m 3 . R di It indicates the amount of radioactive nuclide i in the soil per unit area that penetrates into the groundwater environment, Bq / m 2 ; Where: L i represents the rate at which the radionuclide i penetrates into the underlying soil, m / s; d represents the thickness of the topsoil.
6. The special public dose assessment method according to claim 5, characterized in that: The thickness of the topsoil is 15cm-30cm.
7. The special public dose assessment method according to claim 1, characterized in that: The calculation of the ingestion internal radiation dose is based on the following formula: Where: DCF ingi The effective dose conversion factor of the ingested radionuclide i to the human body, Sv / Bq; U ingi For the above-mentioned special public individuals, ingestion through ingestion 3 H and 14 The amount of radionuclide i other than C, Bq / a.
8. The special public dose assessment method according to claim 7, characterized in that: The U ingi The calculation takes into account the different types of consumer goods and adopts the following formula: Where: U r Rice consumption of the target special public individuals, kg / a; U f The surface consumption of the target special public individuals, kg / a; U o Consumption of other potatoes and beans by the target special public individuals, kg / a; U lv Leafy vegetable consumption of the target special public individuals, kg / a; U rv Consumption of root vegetables by the target special public individuals, kg / a; U fv The consumption of fruit and vegetables by the target special public individuals, kg / a; U av Consumption of aquatic vegetables for the target special public individuals, kg / a; U p The pork consumption of the target special public individuals, kg / a; U m The amount of mutton consumed by the target special public individuals, kg / a; U b The beef consumption of the target special public individuals, kg / a; U q The poultry meat consumption of the target special public individuals, kg / a; U y Fish consumption by the target specific public individuals, kg / a; U e The egg consumption of the target special public individuals, kg / a; U m Milk consumption of the target special public individuals, kg / a; U s The fruit consumption of the target special public individuals, kg / a; U w The drinking water consumption of the target special public individuals, kg / a; U t The amount of soil accidentally ingested by the target special public individuals, kg / a; C xi is the concentration of the radionuclide i in the X-type food or other articles, in Bq / kg or Bq / L, where X is a subscript representing different types of food or other objects, and the same as consumption; F x The share of food and other items of category X originating from the evaluation area; t r ,t f ,t o is the time interval from harvest to consumption of rice, noodles and other crops, d; t lv ,t rv ,t fv ,t av The time interval from harvesting to consumption of leafy, root, tuber, fruit, and aquatic vegetables is d; t p ,t m ,t b ,t q is the time interval from the slaughter of meat-producing animals to their consumption, d; t m is the time interval from milking to milk consumption, d; t e is the time interval from egg laying / collecting to egg consumption, d; r is the processing factor (translocation factor).
9. The special public dose assessment method according to claim 1, characterized in that: The collection of radioactive dose assessment parameter data of the target special public includes: The nuclear facility effluent emission data, emission source characteristic data, meteorological parameters, population distribution, target special public food consumption data (food source and intake data), target special public living habits (residence factor setting), working conditions and intensity parameters (for subsequent breathing rate selection), dose conversion factors, and bioconcentration parameters.
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