CN112634114A - Radiation environment management and evaluation method and system - Google Patents
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Abstract
The invention provides a radiation environment management and evaluation method and a radiation environment management and evaluation system, wherein the system comprises a site environment characteristic data module, a nuclear facility characteristic data module, an effluent monitoring data management module, an environment monitoring data management module, a gas-carrying effluent migration and diffusion simulation module and a radiation environment influence evaluation module; the invention manages the environment monitoring data and the effluent monitoring data based on the accurate position relation of the effluent discharge point and the effluent receiving point provided by the geographic information system, adopts the atmospheric diffusion model and the radiation dose estimation model to establish the radiation environment influence relation between the discharge point and the effluent receiving point, and can realize the statistical analysis of the facility effluent and the environment monitoring data and the radiation environment influence evaluation.
Description
Technical Field
The invention relates to the technical field of radiation environment management and radiation environment influence, in particular to a radiation environment management and evaluation method and system.
Background
The nuclear facilities can carry out effluent monitoring and environmental monitoring in the operation process, a large amount of monitoring data can be accumulated along with the time, the monitoring data can be generally summarized and reported to a superior management department in a monitoring report form regularly, statistics and analysis of the data and further mining and application of data for many years are less, how to effectively utilize the effluent and environmental monitoring data and use the data for radiation environment influence evaluation are needed, and the method is a direction which needs attention to improve the use efficiency of the monitoring data and improve the radiation environment management and evaluation level.
Tritium is contained in effluent discharged from part of nuclear facilities,14C、129I、85The special nuclides such as Kr are different from the conventional nuclides in the aspects of transfer rules in the environment and the human body and irradiation ways to the human body, and the particularity of the current commonly-used radiation environment influence evaluation system is not fully considered.
In summary, in order to further improve the radiation environment management level of the nuclear facility, it is necessary to enhance scientific management and effective utilization of radiation monitoring data such as effluent and environmental monitoring, and therefore, it is necessary to establish a set of radiation environment management and evaluation system.
Disclosure of Invention
Aiming at the defects in the prior art, the invention aims to provide a radiation environment management and evaluation method and system, which are used for scientifically managing and effectively utilizing radiation monitoring data such as effluents and environment monitoring.
In order to achieve the purpose, the technical scheme adopted by the invention is as follows:
in a first aspect, the present invention provides a radiation environment management and evaluation method, including:
acquiring parameters of a discharge port of an airborne effluent in a nuclear facility plant area and position coordinates of the discharge port;
obtaining effluent monitoring data for each vent airborne effluent vent;
acquiring human mouth distribution and resident food consumption data within an evaluation range;
acquiring atmospheric diffusion factors of a nuclear facility discharge port;
and inputting the parameters of the gas-carrying effluent discharge port, the position coordinates of the discharge port, effluent monitoring data, population distribution, resident food consumption data and atmospheric diffusion factors of the nuclear facility discharge port into a conventional nuclide dose estimation model to calculate the effective dose of the public.
In one possible implementation, the method further comprises: inputting the parameters of the discharge port of the gas-carrying effluents, the position coordinates of the discharge port, the monitoring data of the effluents, the population distribution, the data of the food consumption of residents and the atmospheric diffusion factors of the discharge port of the nuclear facility into a special nuclide dose estimation model for calculating the personal effective dose of the public, wherein the special nuclides are nuclide tritium, nuclide-hydrogen-nitrogen-,14C、129I and85Kr。
in a second aspect, the present invention provides a radiation environment management and evaluation system, including:
the plant site environmental characteristic data module can statistically analyze population distribution data of different age groups at different positions and distances in an evaluation range and consumption statistical data of various foods of different age groups, and is used for statistically analyzing meteorological data of a plant site area to generate meteorological data which can be used for calculating an atmospheric diffusion model;
the nuclear facility characteristic data module is used for generating discharge port data of a plant area plane position of the nuclear facility and a gas-carrying effluent discharge port parameter;
an effluent monitoring data management module for generating effluent monitoring data for each vent airborne effluent vent;
the environment monitoring data management module is used for counting, analyzing and managing monitoring results of different environment media;
the airborne effluent migration and diffusion simulation module is used for calculating an atmospheric diffusion factor of a nuclear facility discharge port, is respectively in communication connection with the nuclear facility characteristic data module, the plant site environment characteristic data module and the effluent monitoring data management module, and is used for acquiring the meteorological data, the discharge port data and the effluent monitoring data;
the radiation environment influence evaluation module is used for calculating the personal effective dose of the public by combining meteorological data, discharge port data, effluent monitoring data and atmospheric diffusion factors of nuclear facility discharge ports into a conventional nuclide dose estimation model; and
and the data management module is used for managing input data, intermediate data and output data in the plant site environment characteristic data module, the nuclear facility characteristic data module, the gas-carrying effluent migration and diffusion simulation module, the effluent monitoring data management module, the environment monitoring data management module and the radiation environment influence evaluation module.
In one possible implementation mode, the radiation environment influence evaluation module is further used for combining meteorological data, discharge outlet data, effluent monitoring data and atmospheric diffusion factors of nuclear facility discharge outlets into a special nuclide dose estimation model to calculate the effective dose of the public person, wherein the special nuclide is a nuclide tritium, a nuclide B, a nuclide C,14C、129i and85Kr。
in a possible implementation manner, the plant site environment characteristic data module comprises plant site natural environment characteristic data and social environment characteristic data, and the natural environment characteristic data comprises plant site characteristic meteorological data and natural protection area distribution condition data.
In one possible implementation, the airborne effluent discharge port parameters include chimney height, chimney internal diameter, outlet flue gas velocity, adjacent building height, and relative position coordinates.
In one possible implementation, the effluent monitoring data management module includes effluent monitoring point locations and statistics and analysis of monitoring results, the monitoring results include nuclide species, nuclide concentrations, and an exhaust emission, and the statistics and analysis include statistics of minimum, maximum, and average values of each nuclide emission concentration at each discharge outlet.
In a possible implementation manner, the environment monitoring data management module includes environment monitoring point locations and statistics and analysis of monitoring results, and the monitoring data includes nuclide concentrations in media such as air, sediment ash, water, soil, sediment, animals and plants, and gamma dose rates at different monitoring point locations; the result statistics comprises and analyzes the statistics of the minimum value, the maximum value and the average value of the monitoring results of the nucleic acid in different media of different monitoring point positions in the evaluation range; and performing trend analysis on the environment monitoring data condition within a certain time on the basis of statistics.
The invention has the beneficial effects that: the invention manages the environment monitoring data and the effluent monitoring data based on the accurate position relation of the effluent discharge point and the effluent receiving point provided by the geographic information system, adopts the atmospheric diffusion model and the radiation dose estimation model to establish the radiation environment influence relation between the discharge point and the effluent receiving point, and can realize the statistical analysis of the facility effluent and the environment monitoring data and the radiation environment influence evaluation.
Drawings
Fig. 1 is a block diagram illustrating a structural principle of a radiation environment management and evaluation system according to an embodiment of the present invention.
In the figure:
100-radiation environment management and evaluation system, 101-site environment characteristic data module, 102-nuclear facility characteristic data module, 103-gas-borne effluent migration and diffusion simulation module, 104-effluent monitoring data management module, 105-data management module, 106-radiation environment influence evaluation module and 107-environment monitoring data management module.
Detailed Description
The invention is described in further detail below with reference to the drawings and the detailed description.
Example one
Referring to fig. 1, the present embodiment provides a radiation environment management and evaluation system 100, which includes an site environment characteristic data module 101, a nuclear facility characteristic data module 102, an effluent monitoring data management module 104, an environment monitoring data management module 107, a airborne effluent migration and diffusion simulation module 103, and a radiation environment influence evaluation module 106.
The site environment characteristic data module 101 includes site natural environment characteristic data and social environment characteristic data. The natural environment characteristic data comprises site characteristic meteorological data and natural protection area distribution condition data, wherein the site characteristic meteorological data are chronologically meteorological data of a representative meteorological station which is continuous for one year in three years, and comprise wind direction, wind speed, precipitation, temperature, humidity, total cloud, low cloud, station pressure and the like; the natural reserve distribution data includes the relative position and distance between the natural reserve and the field site within the evaluation range. The social environment characteristic data comprises population distribution data of different age groups in an evaluation range and food consumption data of different age groups. And inputting population survey data of different orientations and distances and proportional structures of different age groups in the evaluation range, wherein the system module can statistically analyze population distribution data of different orientations and distances and different age groups in the evaluation range. The consumption statistical data of various foods of different age groups in the evaluation range are input, and the system module can statistically analyze the recipes of different age groups in the evaluation range and the shares from the evaluation area range. The meteorological data (wind direction, wind speed, precipitation, temperature, humidity, total cloud, low cloud, station pressure and the like) and station information (longitude and latitude, observation height, station number) of a typical meteorological station are input, and a system module can perform statistical analysis to form a meteorological data format which can be used for calculating an atmospheric diffusion model.
The nuclear facility characteristic data module 102 comprises plant floor plan layout, key parameters and positions of gas-borne effluent discharge ports; key parameters of the discharge port of the airborne effluent comprise the height of a chimney, the inner diameter, the smoke velocity of an outlet, the height of a nearby building and relative position coordinates; which may form a vent data format for atmospheric diffusion model calculations and radiation environment impact evaluation.
The effluent monitoring data management module 104 comprises effluent monitoring point positions, statistics and analysis of monitoring results; the effluent monitoring result comprises nuclide species, nuclide concentration and exhaust amount; the result statistics and analysis comprises the statistics of the minimum value, the maximum value and the average value of the emission concentration of various nuclides at each discharge port, the statistics of the emission amount of various nuclides at each discharge port and the statistics of the total radioactive emission amount at each discharge port; and carrying out trend analysis on the effluent discharge condition in a certain time on the basis of statistics. By inputting effluent monitoring data of each gas-borne effluent discharge port, such as the discharge port number, the exhaust air volume and the discharge concentration (minimum value, maximum value and average value) of each nuclide monitored each time, the system module can perform statistical analysis and management on the effluent discharge data, perform statistics on the discharge volume and the variation trend of different nuclides of each chimney in different time periods, perform statistics on the discharge volume and the variation trend of gas-borne effluents in each chimney in different time periods, and perform statistics on the discharge volume and the variation trend of gas-borne effluents in different time periods of a facility with a plurality of discharge ports; meanwhile, a release source item data format for the radiation environment influence evaluation module 106 may also be formed.
The environment monitoring data management module 107 comprises environment monitoring point positions and statistics and analysis of monitoring results; the environment monitoring data comprises the nuclide concentrations in air, settled ash, water, soil, sediment, animals and plants and other media at different monitoring point positions and the gamma dose rate; the result statistics comprises and analyzes the statistics of the minimum value, the maximum value and the average value of the monitoring results of the nucleic acid in different media of different monitoring point positions in the evaluation range; and performing trend analysis on the environment monitoring data condition within a certain time on the basis of statistics.
The airborne current effluent migration and diffusion simulation module 103 comprises an atmospheric migration and diffusion model and can calculate atmospheric diffusion factors within an evaluation range; the atmospheric migration diffusion model can be used for calculating atmospheric migration diffusion of different types of emission sources such as point sources, surface sources and body sources, and can also be used for simultaneously calculating a plurality of emission sources. The calculated exhaust ports are determined by inputting, the parameter data of the chimney height, the inner diameter, the outlet flue gas velocity, the height and the relative position of the adjacent building and the like of the corresponding exhaust ports in the nuclear facility characteristic data module 102 are called, the meteorological parameter data of the site environment characteristic data module 101 are called, and the corresponding atmospheric diffusion factors are calculated by combining with the atmospheric diffusion model and are used for the radiation environment influence evaluation module 106.
The radiation environment impact evaluation module 106 includes a conventional species dose estimation model and a special species dose estimation model. The radiation environment influence evaluation module 106 can calculate the personal doses of air immersion external irradiation, surface deposition external irradiation, inhalation internal irradiation and ingestion internal irradiation of residents caused by different nuclides and the total effective dose of individuals according to the food consumption data of population and residents of different age groups within the evaluation range of the site environment characteristic data module 101, the discharge port data of the nuclear facility characteristic data module 102, the nuclide discharge data of different discharge points of the effluent monitoring data management module 104 and the atmospheric diffusion factor data of the air carrier effluent migration diffusion simulation module 103. Public individual effective dose calculation is carried out by calling discharge port data of the nuclear facility characteristic data module 102, effluent monitoring management data of each discharge port in the effluent monitoring data management module 104, population distribution and resident food consumption data of the site environment characteristic data module 101 and atmospheric diffusion factor data of the airborne effluent migration and diffusion simulation module 103, and combining a conventional nuclide dose estimation model and a special nuclide dose estimation model. Wherein the conventional nuclide dose estimation module may calculate personal doses of public air-submerged external irradiation, surface sediment external irradiation, inhalation internal irradiation, and ingestion internal irradiation caused by conventional nuclides in airborne effluents. The special nuclide dose estimation module can calculate the public inhalation internal irradiation and food caused by tritium in the airborne effluentsThe dose of the individual is irradiated in the interior,14c, the air immersion of the public, the inhalation dose, and the ingestion dose,129i dose of the general public by air immersion external irradiation, surface deposition external irradiation, inhalation internal irradiation and ingestion internal irradiation personal dose.85The air immersion of the public by Kr irradiates individual doses. The calculation result can output the annual average individual effective dose of each subregion in the evaluation range, the contribution ratio of different nuclides to the maximum individual effective dose in the evaluation range, the contribution ratio of different irradiation ways to the maximum individual effective dose in the evaluation range, the annual collective dose of each subregion in the evaluation range and the total collective dose in the evaluation range.
The data management module 105 is used for managing input data, intermediate data and output data in the plant site environment characteristic data module 101, the nuclear facility characteristic data module 102, the gas-borne effluent migration and diffusion simulation module 103, the effluent monitoring data management module 104, the environment monitoring data management module 107 and the radiation environment influence evaluation module 106, and the data management module 105 includes storage, output and query of various data.
Example two
The embodiment provides a radiation environment management and evaluation method, which comprises the following steps:
s1, acquiring parameters of a discharge port of an airborne effluent in a nuclear facility plant area and position coordinates of the discharge port; key parameters of the discharge port of the airborne effluent comprise chimney height, chimney inner diameter, outlet flue gas velocity, height of a nearby building and relative position coordinates, wherein the relative position is the relative position of the nearby building relative to the discharge port;
s2, obtaining effluent monitoring data of each discharge port of the airborne effluent discharge ports; monitoring by using the effluent monitoring data management module 104, the effluent monitoring results include nuclide species, nuclide concentration, and exhaust emission; the result statistics and analysis comprises the statistics of the minimum value, the maximum value and the average value of the emission concentration of various nuclides at each discharge port, the statistics of the emission amount of various nuclides at each discharge port and the statistics of the total radioactive emission amount at each discharge port; performing trend analysis on the effluent discharge condition within a certain time on the basis of statistics;
s3, acquiring human mouth distribution and resident food consumption data within the evaluation range; by inputting the population survey data of different orientations and distances and the proportional structure of different age groups within the evaluation range into the site environment characteristic data module 101, the system module can statistically analyze the population distribution data of different orientations and distances and different age groups within the evaluation range. The consumption statistical data of various foods of different age groups in the evaluation range are input, and the system module can statistically analyze the recipes of different age groups in the evaluation range and the shares from the evaluation area range;
s4, acquiring atmospheric diffusion factors of the nuclear facility discharge port; inputting a determined and calculated discharge port in the airborne effluent migration and diffusion simulation module 103, calling the parameter data of chimney height, inner diameter, outlet flue gas velocity, height and relative position of a nearby building and the like of the corresponding discharge port in the nuclear facility characteristic data module 102, calling the meteorological parameter data of the site environment characteristic data module 101, and calculating a corresponding atmospheric diffusion factor by combining an atmospheric diffusion model;
s5, inputting the parameters of the air-borne effluent discharge port, the position coordinates of the discharge port, effluent monitoring data, population distribution, resident food consumption data and atmospheric diffusion factors of the nuclear facility discharge port into a conventional nuclide dose estimation model to calculate the effective dose of the public; in another embodiment, the parameters and position coordinates of the discharge port of the airborne effluents, the effluent monitoring data, the population distribution and the resident food consumption data and the atmospheric diffusion factor of the discharge port of the nuclear facility are also input into a special nuclide dose estimation model for calculating the personal effective dose of the public, wherein the special nuclide is nuclide tritium, nuclide specific diffusion factor, and the like,14C、129I and85Kr。
it will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is intended to include such modifications and variations.
Claims (8)
1. A radiation environment management and evaluation method is characterized by comprising the following steps:
acquiring parameters of a discharge port of an airborne effluent in a nuclear facility plant area and position coordinates of the discharge port;
obtaining effluent monitoring data for each vent airborne effluent vent;
acquiring human mouth distribution and resident food consumption data within an evaluation range;
acquiring atmospheric diffusion factors of a nuclear facility discharge port;
and inputting the parameters of the gas-carrying effluent discharge port, the position coordinates of the discharge port, effluent monitoring data, population distribution, resident food consumption data and atmospheric diffusion factors of the nuclear facility discharge port into a conventional nuclide dose estimation model to calculate the effective dose of the public.
2. The method of claim 1, further comprising: inputting the parameters of the discharge port of the gas-carrying effluents, the position coordinates of the discharge port, the monitoring data of the effluents, the population distribution, the data of the food consumption of residents and the atmospheric diffusion factors of the discharge port of the nuclear facility into a special nuclide dose estimation model for calculating the personal effective dose of the public, wherein the special nuclides are nuclide tritium, nuclide-hydrogen-nitrogen-,14C、129I and85Kr。
3. a radiation environment management and evaluation system, the system comprising:
the plant site environmental characteristic data module can statistically analyze population distribution data of different age groups at different positions and distances in an evaluation range and consumption statistical data of various foods of different age groups, and is used for statistically analyzing meteorological data of a plant site area to generate meteorological data which can be used for calculating an atmospheric diffusion model;
the nuclear facility characteristic data module is used for generating discharge port data of a plant area plane position of the nuclear facility and a gas-carrying effluent discharge port parameter;
an effluent monitoring data management module for generating effluent monitoring data for each vent airborne effluent vent;
the environment monitoring data management module is used for counting, analyzing and managing monitoring results of different environment media;
the airborne effluent migration and diffusion simulation module is used for calculating an atmospheric diffusion factor of a nuclear facility discharge port, is respectively in communication connection with the nuclear facility characteristic data module, the plant site environment characteristic data module and the effluent monitoring data management module, and is used for acquiring the meteorological data, the discharge port data and the effluent monitoring data;
the radiation environment influence evaluation module is used for calculating the personal effective dose of the public by combining meteorological data, discharge port data, effluent monitoring data and atmospheric diffusion factors of nuclear facility discharge ports into a conventional nuclide dose estimation model; and
and the data management module is used for managing input data, intermediate data and output data in the plant site environment characteristic data module, the nuclear facility characteristic data module, the gas-carrying effluent migration and diffusion simulation module, the effluent monitoring data management module, the environment monitoring data management module and the radiation environment influence evaluation module.
4. The system of claim 3, wherein the radiation environment effect evaluation module further comprises a module for calculating the personal effective dose of the public by combining the meteorological data, the discharge data, the effluent monitoring data, and the atmospheric diffusion factor of the nuclear facility discharge into a model for estimating the dose of a specific nuclide, wherein the specific nuclide is a nuclide tritium, a nuclide of a specific nuclide of the atmospheric diffusion factor of the nuclear facility discharge,14C、129I and85Kr。
5. the system according to claim 3 or 4, wherein the plant site environment characteristic data module comprises plant site natural environment characteristic data and social environment characteristic data, and the natural environment characteristic data comprises plant site characteristic meteorological data and natural protection area distribution data.
6. The system of claim 3, wherein the airborne effluent discharge port parameters include chimney height, chimney internal diameter, outlet flue gas velocity, adjacent building height, and relative position coordinates.
7. The system of claim 3, wherein the effluent monitoring data management module comprises statistics and analysis of effluent monitoring sites and monitoring results, the monitoring results comprising nuclide species, nuclide concentrations, and outgassing amounts, the statistics and analysis comprising nuclide emission concentration minimum, maximum, and mean statistics for each vent.
8. The system of claim 3, wherein the environmental monitoring data management module comprises statistics and analysis of environmental monitoring point locations and monitoring results, and the monitoring data comprises nuclide concentrations in media such as air, sediment ash, water, soil, sediment, animals and plants, and gamma dose rates at different monitoring point locations; the result statistics comprises and analyzes the statistics of the minimum value, the maximum value and the average value of the monitoring results of the nucleic acid in different media of different monitoring point positions in the evaluation range; and performing trend analysis on the environment monitoring data condition within a certain time on the basis of statistics.
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| CN111999754A (en) * | 2020-07-10 | 2020-11-27 | 中国辐射防护研究院 | Evaluation system based on nuclear facility airborne effluent monitoring data |
| CN112000922A (en) * | 2020-07-10 | 2020-11-27 | 中国辐射防护研究院 | Special nuclide radiation environment influence evaluation system for post-treatment plant |
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