CN111999754B - Evaluation system based on nuclear facility airborne effluent monitoring data - Google Patents
Evaluation system based on nuclear facility airborne effluent monitoring data Download PDFInfo
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Abstract
The invention discloses an evaluation system based on nuclear facility airborne effluents monitoring data, which comprises the following steps: the air-borne effluent discharge information base is used for storing the name of a nuclear facility unit and discharge port information; the effluent monitoring method information base is used for storing analysis and measurement methods, monitoring instruments, detection limits and monitoring time used by each nuclide monitoring sample; an airborne effluent database for storing annual monitoring data for each discharge port of each facility; and the effluent monitoring and evaluating database is used for calculating the public dosage caused by each nuclide based on the airborne effluent discharge information base, the effluent monitoring method information base and the airborne effluent database. The invention can complete the storage of the discharge data of the airborne effluents of various discharge ports of the nuclear facilities and the estimation of the total discharge amount through the airborne effluent discharge information base and the effluent monitoring method information base, and can realize the public radiation influence caused by all discharge ports of a single discharge port and multiple facilities through the airborne effluent discharge information base.
Description
Technical Field
The invention relates to the field of radiation environment influence evaluation, in particular to an evaluation system based on nuclear facility airborne effluents monitoring data.
Background
The emission of radioactive contaminants during operation of the nuclear facility should not exceed the emission limits approved by regulatory authorities. The total amount of emissions requested by the nuclear facility will be a regulatory target for the actual operation of the facility.
The evaluation management of nuclear facilities requires that the nuclear facilities provide the total emission amount of radioactive effluents in an environmental impact evaluation report in site selection, construction and operation stages and gradually optimize the emission amount. When the nuclear facility is evaluated in environmental influence in the site selection, construction and operation stages, the emission of radioactive pollutants is estimated according to a material balance algorithm, an air volume-concentration method, an operation volume method, a release factor method and the like based on a design process of engineering. The evaluation results are relatively conservative when evaluated by design values and evaluation values. For a large nuclear base, when a plurality of nuclear facility construction projects are evaluated by adopting a conservative release source project, dosage results are excessively conservative, and application of the total emission amount of subsequent construction projects is influenced. Therefore, in the practical engineering application process, it is a more accurate method to use the actual emission amount of the facility to calculate the total emission amount of the base. In order to judge and ensure that the pollutants discharged by the nuclear facility operation meet the emission total limit value, the nuclear facility unit periodically carries out daily monitoring on the effluent, records the emission monitoring result of the radioactive pollutants and estimates the emission total of the radioactive pollutants.
Nuclear facilities have been operating for years to accumulate large amounts of effluent monitoring data. And the effluent data volume is complicated and large, the effluent data comprises monitoring data of multiple facilities, multiple discharge ports, multiple nuclides and multiple years, the classified storage of the data of the discharge ports is completed through a large amount of statistical data, and pollutant discharge source items of the nuclear facilities are obtained. And acquiring the discharge condition of each discharge port according to a large amount of effluent statistical results, and visually reflecting the operating condition of the facility.
In addition, the data of the total amount of nuclides released in the total emission amount of the whole nuclear base and the influence of the total nuclear base emission and which nuclides are the key nuclides of the caused public dose are not known at present when the emission amount is applied before the nuclear facility construction.
Through the construction of the system, the total emission amount of the respective discharge outlets of the nuclear facility can be obtained firstly so as to obtain the actual operation condition of the single facility, the radiation dose of the public caused by the discharge of the single facility is calculated, and the key emission nuclide of the facility can be obtained. And scientific basis is provided for later radiation safety supervision and monitoring plan formulation. Secondly, knowing the source of the release at each discharge outlet of the nuclear base, it is possible to understand the radiation environment level around the base, the radiation impact of the whole base operation on the public, and the cumulative impact of all the discharge outlets on the surrounding environment. Helps to acquire key nuclides influenced by public radiation caused by the nuclide on a nuclear basis, the operation unit is helped to better perform the total amount management.
At present, a statistical system of nuclear facility effluent data is developed at home, but an evaluation system based on a large amount of nuclear facility effluent monitoring statistical data is not established.
Disclosure of Invention
Aiming at the defects in the prior art, the invention aims to provide an evaluation system based on nuclear facility airborne effluent monitoring data, which can realize public radiation dose evaluation based on the nuclear facility airborne effluent monitoring data.
In order to realize the purpose, the technical scheme adopted by the invention is as follows:
an assessment system based on nuclear facility airborne effluent monitoring data, comprising:
an airborne effluent discharge information base for storing nuclear facility unit names and discharge port information, the discharge port information comprises a facility name, a discharge port number, a discharge height and discharged nuclides;
the effluent monitoring method information base is used for storing analysis and measurement methods, monitoring instruments, detection limits and monitoring time used by each nuclide monitoring sample;
the system comprises an airborne effluent database, a data acquisition and processing unit and a data processing unit, wherein the airborne effluent database is used for storing the monitoring data of each year of each discharge port of each facility, and the monitoring data comprises the name of a nuclear facility unit, the name of the facility, the serial number of a discharge point, monitoring time, monitoring nuclides, monitoring results, monitoring units, actual exhaust air volume and air volume units;
and the effluent monitoring and evaluating database is used for calculating the public dosage caused by each nuclide based on the airborne effluent emission information base, the effluent monitoring method information base and the airborne effluent database.
Further, the evaluation system based on the nuclear facility airborne current effluent monitoring data is characterized in that each facility is divided into a uranium mine smelting facility, a nuclear power plant, a nuclear fuel circulation facility and a three-waste treatment facility according to types; the airborne effluent database is also used for counting the key nuclides of each facility according to the difference of the key nuclides of the effluents of different facilities;
gas-borne effluent monitoring nuclides of uranium ore metallurgy facilities comprise U, radon and radon daughters; airborne effluent monitoring nuclides for nuclear power plants include 3 H、 14 C. Total α, total β; the monitoring nuclides of the gas-borne effluents of the nuclear fuel circulation facility comprise U, total alpha and total beta; airborne effluent monitoring nuclides for three waste treatment facilities including 85 Kr、 90 Sr、 137 Cs、 239 Pu、 3 H、 14 C、 129 I。
Further, the system for evaluating the nuclear facility airborne effluent monitoring data is characterized in that the airborne effluent database is further used for obtaining the variation range and the average emission concentration of pollutants in each year and historical operation period according to different emission ports;
the average emission concentration at a certain emission port is calculated by the following formula:
C 1,i1 : the 1 st group monitoring concentration result of the nuclide i discharged from the discharge port;
C 1,in : the nth group of monitoring concentration results of the nuclide i discharged by the discharge port;
n: the number of monitoring data, n is a positive integer.
Further, the system for evaluating the nuclear facility gas-borne effluent monitoring data is characterized in that the gas-borne effluent database is also used for estimating the annual emission amount of single nuclides at each discharge port of each facility, calculating the annual emission amount of all the monitored nuclides at each discharge port of each facility, and summarizing the total emission amount during the operation period of each facility;
the annual emission of a single nuclide at each discharge port of each facility was calculated by the following formula:
Q i ＝C i ×Q w (2)
Q i : annual emission of nuclide i, bq/a;
C i : annual average concentration of nuclide i, bq/m 3 ；
Q w : the annual actual air discharge volume m of the discharge port 3 /a。
Further, the evaluation system based on the nuclear facility airborne effluent monitoring data is also used for inquiring different discharge ports of each nuclear facility unit, the annual discharge amount and the total discharge amount of each nuclide.
Further, an assessment system as described above based on nuclear facility airborne effluent monitoring data, the effluent monitoring assessment database comprising:
the query output module is used for receiving the nuclear facility name, the nuclide name, the discharge port name and/or the monitoring time input by a user, outputting the total discharge amount of each nuclide, and outputting the historical radiation dose evaluation result of each discharge port of each facility;
the nuclide information module is used for storing basic information of each nuclide, and the basic information comprises information parameters of nuclide names, inhalation dosage rate conversion factors, air immersion external irradiation conversion factors, surface deposition external irradiation conversion factors and ingestion dosage conversion factors;
the system comprises a site data module, a site evaluation range data module and a population distribution data module, wherein the site data module is used for storing the recipe data and the population distribution data of the site evaluation range, the population distribution data comprises the names of residents, the relative site distance and the direction, and the recipe data comprises the annual intake of various products;
the atmospheric diffusion module is used for storing site area meteorological parameters, including average wind speed, height of an adjacent building and minimum windward sectional area of the adjacent building, and calculating an atmospheric diffusion factor according to the site area meteorological parameters, wherein the atmospheric diffusion adopts a dilution mode without considering the lifting of smoke plume;
the release source item module is used for calling the name of a nuclear facility unit, the number of a discharge point, the name of a nuclide, the annual discharge amount and the discharge time in the airborne carrier effluent database, and selecting a release source item needing to be calculated, wherein the release source item comprises a single nuclide, a single discharge port and the whole nuclear base;
and the dose evaluation module is used for calculating the public dose caused by each nuclide based on the query output module, the nuclide information module, the site data module, the atmospheric diffusion module and the release source item module.
Further, the system for evaluating nuclear facility airborne effluent monitoring data is described above, wherein the atmospheric diffusion module is specifically configured to:
1) If the height H of the emission source is greater than 2.5 times the height H of the next highest building b I.e. H>2.5H b Then, the atmospheric diffusion factor is calculated by the following formula:
C air，i (x) The method comprises the following steps Concentration of a nuclide i in air, bq/m, at a distance x from the release point x 3 ；
Q i : the release rate of the nuclide i, bq/s;
D i : atmospheric diffusion factor, s/m, of nuclide i 3 ；
P p : taking 0.25 of the time share of the wind blowing to the sector position p where the receiving point is located in one year;
f: releasing a Gaussian diffusion factor of height, namely emission source height H, 1/m at a downwind distance release point x 2 ；
u a : annual average wind speed, m/s, over the release height;
h: emission source height, m;
H b : height of adjacent highest building, m;
x: distance, m, from the release point to the calculation point;
u in the formula (3) is obtained by calculation through the following formula a ：
u 10 : the wind speed at the height of 10m from the ground is m/s;
h: emission source height, m;
n: a wind profile coefficient;
f in formula (3) is calculated by the following formula:
x: distance, m, from the release point to the calculation point;
σ z : vertical diffusion parameter, m;
if H is less than or equal to 45m, the formula (5)
2) If the height H of the emission source is less than or equal to 2.5H b And is and
the atmospheric diffusion factor is calculated by the following formula:
C air，i (x) The method comprises the following steps Concentration of a nuclide i in air, bq/m, at a distance x from the release point x 3 ；
Q i : the release rate of the nuclide i, bq/s;
D i : atmospheric diffusion factor, s/m, of nuclide i 3 ；
P p : the time share of the fan-shaped direction p of the wind blowing to the receiving point in one year is 0.25;
b: gauss diffusion factor at downwind distance x, 1/m 2 ；
u a : annual average wind speed, m/s, over the release height;
h: emission source height, m;
H b : height of adjacent highest building, m;
A b : cross sectional area, m, of the next highest building 2 ；
x: the distance, m, from the release point to the computation point;
b in formula (6) is calculated by the following formula:
σ z : vertical diffusion parameter, m;
A b : cross sectional area, m, of the next highest building 2 ；
x: distance, m, from the release point to the calculation point;
3) If the height H of the emission source is less than or equal to 2.5H b And is and
and if the receiving point is not on the surface of the building where the releasing point is located, calculating the atmospheric diffusion factor by the following formula:
C air，i (x) The method comprises the following steps Concentration of nuclide i in air at a distance x from the release point, bq/m 3 ；
Q i : the release rate of the nuclide i, bq/s;
D i : atmospheric diffusion factor, s/m, of nuclide i 3 ；
P p : taking 0.25 of the time share of the wind blowing to the sector position p where the receiving point is located in one year;
u a : annual average wind speed, m/s, over the release height;
k: taking an empirical constant of 1m;
h: emission source height, m;
H b : height of adjacent highest building, m;
A b : cross sectional area, m, adjacent to the highest building 2 ；
x: distance, m, of the release point to the calculation point.
Further, the evaluation system based on the nuclear facility airborne effluent monitoring data as described above, the dose evaluation module calculates the public dose caused by each nuclide, the public dose caused by each nuclide includes the external exposure dose of surface deposition, the external exposure dose of air immersion, the exposure dose of food intake, and the exposure dose of inhalation, and is calculated by the following formula:
H E(atoms),i (x)＝H E(inh),i (x)+H E(ex,cloud),i (x)+H E(ex,deposit),i (x)+H E(ing),f,r,i (x) (10)
H E(inh),i (x) The method comprises the following steps The inhaled internal radiation dose Sv of the nuclide i;
H E(ing),f,r,i (x) The method comprises the following steps The dose Sv of irradiation in the ingestion of the nuclide i;
H E(ex,cloud),i (x) The method comprises the following steps The air immersion external irradiation dose of the nuclide i, sv;
H E(ex,deposit),i (x) The method comprises the following steps The surface deposit external dose, sv, of nuclide i.
Further, an evaluation system based on nuclear facility airborne effluent monitoring data as described above,
1) The inhaled internal radiation dose is calculated by the following formula:
H E(inh),i (x) The method comprises the following steps The inhaled dose of the nuclide i, sv, at a distance x from the release point;
C air,i (x) (ii) a Concentration of nuclide i in air at a distance x from the release point, bq/m 3 ；
D inh,i : an inhaled dose conversion factor for nuclide i, sv/Bq;
I inh : respiration rate, m 3 /d；
86400: conversion factor, s/d;
O ann : annual residence time, 3.15X 10 7 s；
x: the distance, m, from the release point to the computation point;
c in the formula (11) is obtained by the following calculation air,i (x)：
C air,i (x) The method comprises the following steps Concentration of a nuclide i in air, bq/m, at a distance x from the release point x 3 ；
Q: release rate, bq/s;
D i : distance of nuclide iDiffusion factor at Release Point x, s/m 3 ；
X: the distance of the release point downwind, km;
n: empirical factor, 1.2% of inert gas and tritium, 14 Taking 1.4 as C and 1.42 as other nuclides;
λ i : decay constant, s, of a nuclide i -1 ；
u a : the wind speed at the release altitude, km/s;
2) The air immersion external irradiation dose is calculated by the following formula:
H E(ex,cloud),i (x)＝C air,i (x)·D ex,cloud,i ·O ann ·(O out +(1-O out )·L cloud ) (13)
H E(ex,cloud),i (x) The method comprises the following steps The plume immersion induced dose, sv/a, of the nuclide i at a distance x from the release point;
O ann : annual residence time, s/a;
D ex,cloud,i : conversion factor of smoke plume immersion dose, sv/(Bq s/m) 3 )；
O out : taking 0.2 of outdoor share;
L cloud : taking 0.2 as a shielding factor of a building;
C air,i (x) The method comprises the following steps Activity concentration of a nuclide i in the air, bq/m, at a distance x from the release point 3 ；
x: the distance, m, from the release point to the computation point;
3) The external irradiation of the surface deposits is calculated by the following formula:
H E(ex,deposit),i (x)＝d i (x)·t discharge ·D ex,deposit,i ·(O out +(1-O out )·L deposit ) (14)
H E(ex,deposit),i (x) The method comprises the following steps External irradiation of surface deposits of nuclide i, sv;
d i (x) The method comprises the following steps Annual average deposition rate of nuclide i, including dry and wet deposition, bq s/m 2 ；
t discharge : deposition time, 3.15X 10 7 s；
D ex,deposit,i : dose conversion factor for nuclide i, sv/(Bq/m) 2 )；
O out : taking 0.2 of outdoor share;
L deposit : taking 0.1 as a building shielding factor;
d in the formula (14) is calculated by the following formula i (x)：
d i (x)＝V T ·C air,i (x) (15)
d i (x) The method comprises the following steps Annual average deposition rate of nuclide i, including dry and wet deposition, bq s/m 2 ；
V T : taking the dry and wet deposition rate, m/s, 0.002 m.s < -1 >;
4) The dose of the ingested radiation was calculated by the following formula:
H E(ing),f,r,i (x)＝C f,i (x)·D ing,i ·F local ·I f,r (16)
H E(ing),f,r,i (x) The method comprises the following steps The ingested dose of nuclide i, sv;
C f,i (x) The method comprises the following steps The concentration of nuclide i in the product is Bq/kg or Bq/L;
D ing,i : an ingestion dose conversion factor of nuclide i, sv/Bq;
F local : a local share of food;
I f,r : yield of food in the region, kg or L;
x: distance, m, of the release point to the calculation point.
The invention has the beneficial effects that: the invention can finish the storage of the discharge data of the airborne effluents of various discharge ports of the nuclear facilities and the estimation of the total discharge amount through the airborne effluent discharge information base and the effluent monitoring method information base, and can realize the public radiation influence caused by all discharge ports of a single discharge port and multiple facilities through the airborne effluent discharge information base.
The invention realizes the evaluation from the storage and the processing of the monitoring data to the public dose influence caused by the monitoring data through the statistics and the analysis of the nuclear facility airborne effluents and the statistics, the analysis and the evaluation functions of the airborne effluents of various types of nuclear facilities, can effectively help the operation units to know the emission conditions of all the facilities and the radiation influence on the public, and can be used as a direct basis for solving the radiation influence of the public on the facility operation.
Drawings
Fig. 1 is a schematic structural diagram of an evaluation system based on nuclear facility airborne effluent monitoring data according to an embodiment of the present invention.
Detailed Description
The invention is described in further detail below with reference to the drawings and the detailed description.
As shown in fig. 1, an evaluation system based on nuclear facility airborne effluent monitoring data comprises: the system comprises a gas-borne effluent discharge information base, an effluent monitoring method information base, a gas-borne effluent database and an effluent monitoring and evaluating database.
(1) Air-borne effluent discharge information base
The airborne effluent discharge information base is used for storing the names of nuclear facility units and the discharge port information of the facilities, and comprises the facility names, the discharge port numbers, the discharge heights and the main discharged nuclides.
(2) Information base of effluent monitoring method
The effluent monitoring method information base is used for storing information such as analysis and measurement methods, monitoring instruments, detection limits of the monitoring instruments, monitoring time and the like for nuclide monitoring sampling.
(3) Airborne effluent database
The airborne effluent monitoring data processing system has a data storage function and can be used for storing annual monitoring data of each discharge port of each facility. Mainly comprises the name of nuclear facility unit, the serial number of emission point, the monitoring nuclide, the monitoring time and the nuclide concentration (C) i ) Exhaust air volume (Q) w ). Nuclear facilities are classified into uranium ore smelting facilities, nuclear power plants, nuclear fuel circulation facilities, and three-waste treatment facilities according to types. And counting the key nuclides of each facility according to the difference of the key nuclides of the effluent of different facilities. For example, the gas-carrying effluents of uranium mining and smelting facilities are U, radon and radon seedsBody, etc.; airborne effluent monitoring nuclides for nuclear power plants 3 H、 14 C. Total α, total β, etc.; the monitoring nuclides of the gas-borne effluents of the nuclear fuel circulation facility are U, total alpha, total beta and the like; the gas-carrying effluent monitoring nuclide of the three-waste treatment facility is 85 Kr、 90 Sr、 137 Cs、 239 Pu、 3 H、 14 C、 129 I, and the like.
The built-in data statistical analysis function of the gas-borne effluent database can provide the variation range and the average emission concentration of pollutants in each year and historical operation period according to different discharge ports.
The average emission concentration is calculated by the formula:
C 1,i1 : 1 group monitoring concentration result of nuclide i discharged from the chimney 1;
C 1,in : n groups of monitoring concentration results of nuclide i emitted by the chimney 1;
n: the amount of data is monitored.
The air current effluent database is internally provided with an emission estimation function, can estimate the annual emission of single nuclides at a certain discharge port, calculates the annual emission of all the monitored nuclides at the discharge port, and summarizes the total emission during the operation of the facility.
Annual emissions were calculated by the following formula:
Q i ＝C i ×Q w (2)
Q i : emission amount of nuclide i, bq/a;
C i : concentration of nuclide i, bq/m 3 ；
Q w : actual amount of exhaust air, m 3 /a。
When the average concentration of the monitoring data is calculated, when the monitoring result is lower than the data (< LLD) of the detection limit of the instrument, the detection limit of the monitoring instrument in the effluent monitoring method information base is automatically called, and 1/2 of the detection limit is used as the monitoring result.
The gas-carrying effluent database is internally provided with a data output function, and can inquire the annual emission amount and the total emission amount of each unit, different discharge ports and each nuclide.
(4) Effluent monitoring and evaluation database
The effluent monitoring and evaluating database is internally provided with an inquiry output module, a nuclide information module, a field address data module, an atmospheric diffusion module, a release source item module and a dose evaluating module.
The query output module is internally provided with a screening function and can input the name of the nuclear facility, the name of the nuclide, the name of the discharge outlet and the monitoring time to output the total discharge amount of each nuclide. Through evaluation and calculation, the output function can realize the radiation dose evaluation result of each discharge outlet of certain nuclear facilities over the years.
The nuclide information module is used for storing basic information of each nuclide, and the basic information comprises information parameters of a nuclide name, an inhalation dosage rate conversion factor (DFinh), an air immersion external irradiation conversion factor (DFclo), a surface deposition external irradiation conversion factor (DFdep) and an ingestion dosage conversion factor (DFing).
And the site data module is used for storing the recipe and population data of the site evaluation range. Population distribution data and recipe data of the factory address evaluation range area can be called during evaluation calculation, the population distribution data mainly comprises names of residential points, relative factory address distances and directions, and the recipe data mainly comprises annual intake of various products.
The atmospheric diffusion module is used for storing meteorological parameters of a plant site area, the average wind speed, the height of an adjacent building and the minimum windward sectional area of the adjacent building, and the atmospheric diffusion adopts a dilution mode without considering the lifting of smoke plume.
1) If the source height is greater than 2.5 times the height H of the next highest building b I.e. H>2.5H b Then, the atmospheric diffusion factor is calculated by the following formula:
C air，i (x) The method comprises the following steps Concentration of a nuclide i in air, bq/m, at a distance x from the release point x 3 ；
Q i : nuclide release rate, bq/s;
D i : atmospheric diffusion factor, s/m 3 ；
P p : the time share of the fan-shaped direction p of the wind blowing to the receiving point in one year is 0.25;
f: release Gauss diffusion factor of height (H) 1/m at x km downwind distance release point 2 ；
u a : annual average wind speed, m/s, over the release height;
h: emission source height, m;
H b : height adjacent to the highest building, m.
U in the formula (3) is obtained by calculation through the following formula a ：
u 10 : the wind speed at the height of 10m from the ground is m/s;
h: emission source height, m;
n: the wind profile coefficient.
The values of the wind profile coefficient n are given in table 1 below.
TABLE 1 wind Profile coefficients
F in formula (3) is calculated by the following formula:
x: the distance, m, from the release point to the computation point;
σ z : vertical diffusion parameter, m.
If H is less than or equal to 45m, the formula (5)
2) If the release height H is less than or equal to 2.5H b And is and
the atmospheric diffusion factor is calculated by the following formula:
C air，i (x) The method comprises the following steps Concentration of a nuclide i in air, bq/m, at a distance x from the release point x 3 ；
Q i : nuclide release rate, bq/s;
D i : atmospheric diffusion factor, s/m 3 ；
P p : taking 0.25 of the time share of the wind blowing to the sector position p where the receiving point is located in one year;
b: gauss diffusion factor at downwind distance x, 1/m 2 ；
u a : annual average wind speed, m/s, over the release height;
h: emission source height, m;
H b : height of adjacent highest building, m;
A b : cross sectional area, m, adjacent to the highest building 2 。
B in formula (6) is calculated by the following formula:
σ z : vertical diffusion parameter, m;
A b : cross sectional area, m, adjacent to the highest building 2 。
3) If the release height H is less than or equal to 2.5H b And is made of
And if the receiving point is not on the surface of the building where the releasing point is located, calculating the atmospheric diffusion factor by the following formula:
C air，i (x) The method comprises the following steps Concentration of nuclide i in air at a distance x from the release point, bq/m 3 ；
Q i : nuclide release rate, bq/s;
D i : atmospheric diffusion factor, s/m 3 ；
P p : the time share of the fan-shaped direction p of the wind blowing to the receiving point in one year is 0.25;
u a : annual average wind speed, m/s, over the release height;
k: taking an empirical constant of 1m;
h: emission source height, m;
H b : height of adjacent highest building, m;
A b : cross sectional area, m, of the next highest building 2 。
And the release source item module calls information such as the name of a nuclear facility unit, a discharge port, a nuclide name, annual discharge capacity, discharge time and the like in the airborne effluent database. The calculated release source term can be selected to be a single nuclide, a single discharge, or the entire nuclear base. The discharge time may be selected to be a year or years.
The dose evaluation module is used to estimate the radiation dose impact of the public using the total effluent discharge. And the dose evaluation module gives public dose evaluation results according to the ways of external irradiation dose of surface deposition, external irradiation dose of air immersion, internal irradiation dose of food and internal irradiation dose of inhalation.
The public dose of nuclides includes external exposure dose for surface deposition, external exposure dose for air immersion, internal exposure dose for ingestion, and internal exposure dose for inhalation. The evaluation model calculation formula using effluent monitoring data is as follows:
H E(atoms),i (x)＝H E(inh),i (x)+H E(ex,cloud),i (x)+H E(ex,deposit),i (x)+H E(ing),f,r,i (x) (10)
H E(inh),i (x) The method comprises the following steps An inhaled internal radiation dose Sv;
H E(ing),f,r,i (x) The method comprises the following steps (iv) an internal radiation dose, sv;
H E(ex,cloud),i (x) The method comprises the following steps The external irradiation dose, sv, is air immersion;
H E(ex,deposit),i (x) The method comprises the following steps External irradiation dose, sv, of surface deposits.
1) The inhaled internal radiation dose is calculated by the following formula:
H E(inh),i (x) The method comprises the following steps The inhaled dose of nuclide i, sv, at a distance x from the release point;
C air,i (x) (ii) a Concentration of nuclide i in air at a distance x from the release point, bq/m 3 ；
D inh,i : an inhaled dose conversion factor for nuclide i, sv/Bq;
I inh : respiration rate, m 3 /d；
86400: conversion factor, s/d;
O ann : annual residence time, 3.15X 10 7 s；
x: distance, m, from the release point to the calculation point;
c in the formula (11) is obtained by the following calculation air,i (x)：
C air,i (x) The method comprises the following steps Concentration of nuclide i in air at a distance x from the release point, bq/m 3 ；
Q: release rate, bq/s;
D i : diffusion factor, s/m, of a nuclide i at a distance x from the release point 3 ；
X: the distance of the release point downwind, km;
n: empirical factor, 1.2% of inert gas and tritium, 14 Taking 1.4 as C and 1.42 as other nuclides;
λ i : decay constant, s, of a nuclide i -1 ；
u a : the wind speed at the release altitude, km/s;
2) The air immersion external irradiation dose is calculated by the following formula:
H E(ex,cloud),i (x)＝C air,i (x)·D ex,cloud,i ·O ann ·(O out +(1-O out )·L cloud ) (13)
H E(ex,cloud),i (x) The method comprises the following steps The plume immersion induced dose, sv/a, of the nuclide i at a distance x from the release point;
O ann : annual residence time, s/a;
D ex,cloud,i : conversion factor of smoke plume immersion dose, sv/(Bq s/m) 3 )；
O out : taking 0.2 of outdoor share;
L cloud : taking 0.2 as a shielding factor of the building;
C air,i (x) The method comprises the following steps Activity concentration of a nuclide i in air, bq/m, at a distance x from the release point 3 ；
3) The external irradiation of the surface deposits is calculated by the following formula:
H E(ex,deposit),i (x)＝d i (x)·t discharge ·D ex,deposit,i ·(O out +(1-O out )·L deposit ) (14)
H E(ex,deposit),i (x) The method comprises the following steps External irradiation of surface deposits of nuclide i, sv;
d i (x) The method comprises the following steps Annual average deposition rate of nuclide i, including dry and wet deposition, bq s/m 2 ；
t discharge : deposition time, 3.15X 10 7 s；
D ex,deposit,i : dose conversion factor for nuclide i, sv/(Bq/m) 2 )；
O out : taking 0.2 of outdoor share;
L deposit : taking 0.1 as a building shielding factor;
d in formula (14) is calculated by i (x)：
d i (x)＝V T ·C air,i (x) (15)
d i (x) The method comprises the following steps Annual average deposition rate of nuclide i, including dry and wet deposition, bq s/m 2 ；
V T : the dry and wet deposition rates, m/s, were 0.002 m.s-1.
4) The dose of the ingested radiation was calculated by the following formula:
H E(ing),f,r,i (x)＝C f,i (x)·D ing,i ·F local ·I f,r (16)
H E(ing),f,r,i (x) The method comprises the following steps The ingested dose of nuclide i, sv;
C f,i (x) The method comprises the following steps The concentration of nuclide i in the product is Bq/kg or Bq/L;
D ing,i : an ingestion dose conversion factor of nuclide i, sv/Bq;
F local : a locally derived portion of the food;
I f,r : food output in kg or L in this area.
Example one
Radioactive nuclide at 1# discharge port of facility a by treating three wastes of plant A 129 For example, the total emission and radiation dose of the nuclide in 2019 are calculated. The storage information format of the air-borne effluent discharge information base is shown inTable 2. The effluent monitoring method information is shown in table 3. The airborne effluent database data storage is shown in table 4.
TABLE 2 airborne effluent discharge information
| Nuclide | Analytical measurement method | Monitoring instrument | Limit of instrumental detection | Monitoring time |
| 129 I | Liquid scintillation spectrometer | 3170 | 1.6Bq/m 3 | 2019 |
| … |
Table 3 effluent monitoring method information
Table 4 airborne effluent database data storage (1 #)
The effluent monitoring and evaluating database calls a nuclide information module to give out nuclides 129 The information parameters of I are shown in Table 5.
TABLE 5 nuclide information Module calls nuclides 129 Information parameter of I
The site data module can call the dietary survey results of the population at the evaluation range (80 km), take the population at the 1km as an evaluation object and call information as shown in the table 6.
Table 6 site data module calls population recipe data at 1km
The atmospheric diffusion module can use meteorological data of the area where the plant A is located in 2019, the calculation of the diffusion factor is completed according to the atmospheric diffusion coefficient mode, and parameter results are shown in the following table 7.
TABLE 7 atmospheric diffusion Module Call Meteorological evaluation parameters
The release source entry module then invokes the airborne effluent database data storage results, see table 4.
The dosage evaluation module calls the data of table 4, table 5, table 6, table 7, and the evaluation result is shown in table 8 according to the effluent dosage evaluation mode. The following calculation results are taken as examples, and the radiation dose of the public caused by each discharge port of each nuclear facility can be output, the radiation effect of the public caused by each facility discharge port can be grasped, and the cumulative effect of the used discharge ports on the surrounding environment can be grasped. The nuclear facility monitoring system helps analyze key nuclides influenced by public radiation due to multiple discharge ports of a nuclear facility, and helps an operation unit to better establish a monitoring scheme and total amount management.
TABLE 8 2019 annual A plant a facility 1# discharge nuclide 129 I-induced M-village public radiation dose result
The implementation of the evaluation system based on the nuclear facility airborne effluent monitoring data can finish the storage of the emission data of various emission ports of the nuclear facility airborne effluents and the estimation of the emission total amount, and the radiation influence of the public caused by a single emission port and all emission ports of multiple facilities can be realized based on the dosage evaluation module.
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 (6)
1. An assessment system based on nuclear facility airborne effluent monitoring data, comprising:
an airborne effluent discharge information base for storing nuclear facility unit names and discharge port information, the discharge port information comprises a facility name, a discharge port number, a discharge height and a discharged nuclide;
the effluent monitoring method information base is used for storing analysis and measurement methods, monitoring instruments, detection limits and monitoring time used by each nuclide monitoring sample;
the air-borne effluent database is used for storing the monitoring data of each year of each discharge port of each facility, and the monitoring data comprises the name of a nuclear facility unit, the name of the facility, the number of a discharge point, monitoring time, a monitoring nuclide, a monitoring result, a monitoring unit, actual air discharge quantity and an air quantity unit;
an effluent monitoring and evaluation database for calculating the public dose caused by each nuclide based on the airborne effluent emission information base, the effluent monitoring method information base and the airborne effluent database;
the effluent monitoring and evaluation database includes:
the query output module is used for receiving the nuclear facility name, the nuclide name, the discharge port name and/or the monitoring time input by a user, outputting the total discharge amount of each nuclide, and outputting the historical radiation dose evaluation result of each discharge port of each facility;
the nuclide information module is used for storing basic information of each nuclide, and the basic information comprises information parameters of nuclide names, inhalation dosage rate conversion factors, air immersion external irradiation conversion factors, surface deposition external irradiation conversion factors and ingestion dosage conversion factors;
the system comprises a site data module, a site evaluation range module and a population distribution module, wherein the site data module is used for storing recipe data and population distribution data of the site evaluation range, the population distribution data comprises names of residential sites, relative site distances and directions, and the recipe data comprises annual intake of various products;
the atmospheric diffusion module is used for storing site area meteorological parameters, including average wind speed, height of an adjacent building and minimum windward sectional area of the adjacent building, and calculating an atmospheric diffusion factor according to the site area meteorological parameters, wherein the atmospheric diffusion adopts a dilution mode without considering the lifting of smoke plume;
the release source item module is used for calling the name of a nuclear facility unit, the number of a discharge point, the name of a nuclide, the annual discharge amount and the discharge time in the airborne carrier effluent database, and selecting a release source item needing to be calculated, wherein the release source item comprises a single nuclide, a single discharge port and the whole nuclear base;
the dose evaluation module is used for calculating public dose caused by each nuclide based on the query output module, the nuclide information module, the site data module, the atmospheric diffusion module and the release source item module;
the dose evaluation module calculates the public dose caused by each nuclide, wherein the public dose caused by each nuclide comprises an external irradiation dose for surface deposition, an external irradiation dose for air immersion, an internal irradiation dose for eating and an internal irradiation dose for inhalation, and is calculated by the following formula:
H E(atoms),i (x)＝H E(inh),i (x)+H E(ex,cloud),i (x)+H E(ex,deposit),i (x)+H E(ing),f,r,i (x) (10)
H E(inh),i (x) The method comprises the following steps The inhaled internal radiation dose, sv, of the nuclide i;
H E(ing),f,r,i (x) The method comprises the following steps (iv) an in-ingestion radiation dose, sv, of the nuclide i;
H E(ex,cloud),i (x) The method comprises the following steps The air immersion external irradiation dose of the nuclide i, sv;
H E(ex,deposit),i (x) The method comprises the following steps The external irradiation dose Sv of the surface deposition of the nuclide i;
1) The inhaled internal radiation dose is calculated by the following formula:
H E(inh),i (x) The method comprises the following steps The inhaled dose of nuclide i, sv, at a distance x from the release point;
C air,i (x) (ii) a Concentration of a nuclide i in air, bq/m, at a distance x from the release point x 3 ；
D inh,i : an inhaled dose conversion factor for nuclide i, sv/Bq;
I inh : respiration rate, m 3 /d；
86400: conversion factor, s/d;
O ann : annual residence time, 3.15X 10 7 s；
x: the distance, m, from the release point to the computation point;
c in the formula (11) is obtained by the following calculation air,i (x)：
C air,i (x) The method comprises the following steps Concentration of a nuclide i in air, bq/m, at a distance x from the release point x 3 ；
Q: release rate, bq/s;
D i : diffusion factor, s/m, of a nuclide i at a distance x from the release point 3 ；
X: the distance of the release point downwind, km;
n: empirical factor, 1.2 of inert gas and tritium, 14 Taking 1.4 as C and 1.42 as other nuclides;
λ i : decay constant, s, of a nuclide i -1 ；
u a : annual average wind speed over release height, km/s;
2) The air immersion external irradiation dose is calculated by the following formula:
H E(ex,cloud),i (x)＝C air,i (x)·D ex,cloud,i ·O ann ·(O out +(1-O out )·L cloud ) (13)
H E(ex,cloud),i (x) The method comprises the following steps The plume immersion induced dose, sv/a, of the nuclide i at a distance x from the release point;
O ann : annual residence time, s/a;
D ex,cloud,i : smoke plume immersion dose conversion factor, sv/(Bqs/m) 3 )；
O out : taking 0.2 of outdoor share;
L cloud : taking 0.2 as a shielding factor of the building;
C air,i (x) The method comprises the following steps Activity concentration of a nuclide i in the air, bq/m, at a distance x from the release point 3 ；
x: the distance, m, from the release point to the computation point;
3) The external irradiation of the surface deposits is calculated by the following formula:
H E(ex,deposit),i (x)＝d i (x)·t discharge ·D ex,deposit,i ·(O out +(1-O out )·L deposit ) (14)
H E(ex,deposit),i (x) The method comprises the following steps External irradiation of surface deposits of nuclide i, sv;
d i (x) The method comprises the following steps Annual average deposition rate of nuclide i, including dry and wet deposition, bqs/m 2 ；
t discharge : deposition time, 3.15X 10 7 s；
D ex,deposit,i : dose conversion factor for nuclide i, sv/(Bq/m) 2 )；
O out : taking 0.2 of outdoor share;
L deposit : taking 0.1 as a building shielding factor;
d in formula (14) is calculated by i (x)：
d i (x)＝V T ·C air,i (x) (15)
d i (x) The method comprises the following steps Annual average deposition rate of nuclide i, including dry and wet deposition, bqs/m 2 ；
V T : taking the dry and wet deposition rate, m/s, 0.002 m.s < -1 >;
4) The dose of the ingested radiation was calculated by the following formula:
H E(ing),f,r,i (x)＝C f,i (x)·D ing,i ·F local ·I f,r (16)
H E(ing),f,r,i (x) The method comprises the following steps The ingested dose of nuclide i, sv;
C f,i (x) The method comprises the following steps The concentration of nuclide i in the product is Bq/kg or Bq/L;
D ing,i : an ingestion dose conversion factor of nuclide i, sv/Bq;
F local : a locally derived portion of the food;
I f,r : yield of food in the region, kg or L;
x: distance, m, of the release point to the calculation point.
2. The system for evaluating airborne effluent monitoring data based on nuclear facilities as claimed in claim 1, wherein said facilities are classified by type into uranium mining and metallurgy facilities, nuclear power plants, nuclear fuel recycling facilities and three waste disposal facilities; the airborne effluent database is also used for counting the key nuclides of each facility according to the difference of the key nuclides of the effluents of different facilities;
the gas-borne effluent monitoring nuclides of uranium ore smelting facilities comprise U, radon and radon daughter; airborne effluent monitoring nuclides for nuclear power plants include 3 H、 14 C. Total alpha, total beta; the monitoring nuclides of the gas-borne effluents of the nuclear fuel circulation facility comprise U, total alpha and total beta; airborne effluent monitoring nuclides for three-waste treatment facilities including 85 Kr、 90 Sr、 137 Cs、 239 Pu、 3 H、 14 C、 129 I。
3. The system of claim 1, wherein the airborne effluent database is further configured to obtain the variation range of the pollutants and the average emission concentration for each year and during the historical operation period according to different emission ports;
the average emission concentration at a certain emission port is calculated by the following formula:
C 1,i1 : the 1 st group monitoring concentration result of the nuclide i discharged from the discharge port;
C 1,in' : the n' th group of the nuclide i discharged from the discharge port monitors the concentration result;
n': the number of monitoring data, n' is a positive integer.
4. The nuclear facility airborne nuclide monitoring data-based evaluation system of claim 1, wherein the airborne nuclide emission database is further configured to estimate an annual emission of a single nuclide at each facility discharge, calculate an annual emission of all monitored nuclides at each facility discharge, and aggregate the total emissions during operation of each facility;
the annual emission of a single nuclide at each discharge of each facility was calculated by the following formula:
Q i '＝C i ×Q w (2)
Q i ': annual emission of nuclide i, bq/a;
C i : annual average concentration of nuclide i, bq/m 3 ；
Q w : the annual actual air discharge volume m of the discharge port 3 /a。
5. The nuclear facility airborne effluent monitoring data-based assessment system according to claim 1, wherein said airborne effluent database is further adapted to query each nuclear facility unit for different discharge ports, annual emissions and total emissions of each nuclide.
6. The system of claim 5, wherein the atmospheric diffusion module is configured to:
1) If the height H of the emission source is greater than 2.5 times the height H of the next highest building b I.e. H>2.5H b Then, the atmospheric diffusion factor is calculated by the following formula:
C air，i (x) The method comprises the following steps Concentration of a nuclide i in air, bq/m, at a distance x from the release point x 3 ；
Q i : the release rate of the nuclide i, bq/s;
D i : atmospheric diffusion factor, s/m, of nuclide i 3 ；
P p : the time share of the fan-shaped direction p of the wind blowing to the receiving point in one year is 0.25;
f: releasing a Gaussian diffusion factor of height, namely emission source height H, 1/m at a downwind distance release point x 2 ；
u a : annual average wind speed, m/s, over the release height;
h: emission source height, m;
H b : height of adjacent highest building, m;
x: distance, m, from the release point to the calculation point;
u in the formula (3) is obtained by the following formula calculation a ：
u 10 : the wind speed at the height of 10m from the ground is m/s;
h: emission source height, m;
n wind (W) : a wind profile coefficient;
f in formula (3) is calculated by the following formula:
x: distance, m, from the release point to the calculation point;
σ z : vertical diffusion parameter, m;
if H is less than or equal to 45m, the formula (5)
2) If the height H of the emission source is less than or equal to 2.5H b And is made of
The atmospheric diffusion factor is calculated by the following formula:
C air，i (x) The method comprises the following steps Concentration of nuclide i in air at a distance x from the release point, bq/m 3 ；
Q i : the release rate of the nuclide i, bq/s;
D i : atmospheric diffusion factor, s/m, of nuclide i 3 ；
P p : the time share of the fan-shaped direction p of the wind blowing to the receiving point in one year is 0.25;
b: gauss diffusion factor at downwind distance x, 1/m 2 ；
u a : annual average wind speed, m/s, over the release height;
h: emission source height, m;
H b : height of adjacent highest building, m;
A b : cross sectional area, m, adjacent to the highest building 2 ；
x: distance, m, from the release point to the calculation point;
b in formula (6) is calculated by the following formula:
σ z : vertical diffusion parameter, m;
A b : cross sectional area, m, adjacent to the highest building 2 ；
x: distance, m, from the release point to the calculation point;
3) If the height H of the emission source is less than or equal to 2.5H b And is and
and if the receiving point is not on the surface of the building where the releasing point is located, calculating the atmospheric diffusion factor by the following formula:
C air，i (x) The method comprises the following steps Concentration of a nuclide i in air, bq/m, at a distance x from the release point x 3 ；
Q i : the release rate of the nuclide i, bq/s;
D i : atmospheric diffusion factor, s/m, of nuclide i 3 ；
P p : the time share of the fan-shaped direction p of the wind blowing to the receiving point in one year is 0.25;
u a : annual average wind speed, m/s, over the release height;
k: taking an empirical constant of 1m;
h: emission source height, m;
H b : height of adjacent highest building, m;
A b : cross sectional area, m, adjacent to the highest building 2 ；
x: distance, m, of the release point to the calculation point.
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| 秦山核电厂实时剂量评价系统的设计、模式、参数与程序;胡二邦 等;《辐射防护》;19940131;第14卷(第1期);第25-32页 * |
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