CN115994690B - Nuclear risk assessment method, system and computer readable medium - Google Patents
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Abstract
The embodiment of the application discloses a nuclear risk assessment method, a system and a computer readable medium, wherein the nuclear risk assessment method comprises the following steps: acquiring detection data; estimating personal radiation doses of the staff based on the detection data; updating the personal dose information file of the staff according to the personal radiation dose of the staff; according to the personal radiation doses of different staff at the same post, estimating the post radiation dose of the corresponding post; estimating task radiation doses of corresponding tasks according to the post radiation doses of different posts of the same task; according to the personal radiation dose, the post radiation dose and the task radiation dose, the nuclear risk assessment is carried out to obtain a nuclear risk assessment result, and the technical problem of single function of the existing nuclear monitoring system can be improved.
Description
Technical Field
The present application relates to the field of radiation protection and radiation security technologies, and in particular, to a nuclear risk assessment method, a nuclear risk assessment system, and a computer readable medium.
Background
With the development of the nuclear industry, people are gradually focusing on professional health and safety management of nuclear related personnel. The international atomic energy institutions and other units sequentially publish a large number of standards, guidelines and related documents. A large amount of work is also done by a plurality of research institutions in the aspects of evaluation and management of radiation risks of nuclear personnel, and the steady, healthy and sustainable development of the nuclear industry is promoted.
In the research and practice process of the prior art, the inventor of the application finds that the existing nuclear-related monitoring system has single function, and is difficult to meet the use requirements of enterprises engaged in nuclear power plants, nuclear element production and other enterprises, nuclear-related staff in hospitals and other specific industries.
Disclosure of Invention
The application provides a nuclear risk assessment method, a nuclear risk assessment system and a computer readable medium, which can improve the technical problem of single function of the existing nuclear monitoring system.
The application provides a nuclear risk assessment method, which comprises the following steps:
step B1, obtaining detection data;
step B2, estimating personal radiation dose of staff according to the detection data;
step B3, updating personal dose information files of staff according to the personal radiation doses of the staff;
step B4, estimating post radiation doses of corresponding posts according to the personal radiation doses of different staff at the same post;
step B5, estimating task radiation doses of corresponding tasks according to the post radiation doses of different posts of the same task; and
and B6, performing nuclear risk assessment according to the personal radiation dose, the post radiation dose and the task radiation dose to obtain a nuclear risk assessment result.
Optionally, in some embodiments of the present application, in the step B1, the detection data includes a punctual source activity of the working area, a distance of the working area from the punctual source, a measurement at an overhead of the working area 24 Na gamma initial count rate, residence time of the working area, and air activity concentration of the nuclide of the working area;
the step B2 comprises the following steps:
step B21, estimating personal gamma dosage of staff according to activity of the point-shaped source of the working area, distance between the working area and the point-shaped source and residence time of the working area;
step B22, according to measurements at the overhead of the working area 24 Na gamma initial count rate, estimated individual neutron dose;
step B23, estimating the irradiation dose in the individual according to the residence time of the working area and the air activity concentration of different nuclides;
and step B24, obtaining personal radiation dose of the staff according to the personal gamma dose, the personal neutron dose and the intra-personal radiation dose.
Optionally, in some embodiments of the present application, the step B21 includes:
step B211, estimating gamma dose of staff in different working areas according to activity of the point source in the working area, distance between the working area and the point source and residence time of the working area, wherein an estimation formula of the gamma dose of the staff in different working areas is as follows:
；
Wherein X is j Gamma dose for the j-th working area, the unit is Gy, j is an integer greater than 0; q (Q) j The unit is Bq for the point source activity of the j-th working area; Γ is a constant 3.42×10 -13 The unit is Gy.m 2 /(h·Bq)；T j The residence time of the jth working area is given in h; r is R j The unit is m, which is the distance between the jth working area and the point source;
step B212, estimating personal gamma dose of staff according to gamma dose of staff in different working areas, wherein an estimation formula of the personal gamma dose is as follows:
；
wherein X is Total (S) Personal gamma dose for staff, in Gy; x is X j The gamma dose for the j-th working region, j being an integer greater than 0.
Optionally, in some embodiments of the present application, the step B22 includes:
step B221, measured from the overhead of the work area 24 The initial counting rate of Na gamma is used for estimating neutron dose of staff in different working areas, and an estimation formula of the neutron dose of the staff in the different working areas is as follows:
；
wherein,,neutron dose of staff in a j-th working area is given in Gy, and j is an integer larger than 0; f (f) j Is the coefficient related to the irradiation and measurement time in the jth working area, and is expressed as s -1 ；D Fj The unit of the absorption dose generated for the unit neutron fluence of the jth working area is Gy cm 2 Neutrons; n (t) 0 ) j Measured at the top of the head for the jth working area 24 Na gamma initial count rate, unitIs neutron s/cm 2 ；
Step B222, estimating personal neutron dose of staff according to neutron dose of staff in different working areas, wherein an estimation formula of the personal neutron dose is as follows:
；
wherein,,personal neutron dose for staff, in Gy; />Neutron dose of staff in the j-th working area is given in Gy, and j is an integer greater than 0.
Optionally, in some embodiments of the present application, the step B23 includes:
step B231, estimating the effective dose of the corresponding nuclide to be accumulated in the corresponding working area according to the residence time of the working area and the air activity concentration of the nuclide, wherein the estimation mode of the effective dose of the corresponding nuclide to be accumulated in the corresponding working area is as follows:
；
wherein E (i) j For the effective dose to be accumulated of the nuclide i in the j-th working area, the unit is mSv, and j is an integer greater than 0; c (C) ij The air activity concentration of the nuclide i in the jth working area is expressed as Bq/m 3 The method comprises the steps of carrying out a first treatment on the surface of the B is the respiration rate of the person, and the unit is m 3 /h；T j The stay time of the staff in the j-th working area is h; e, e i The unit is mSv/Bq, which is the dose conversion coefficient of the nuclide i;
Step B232, estimating the sum of the effective doses of the corresponding nuclides to be integrated in different working areas according to the effective doses of the corresponding nuclides to be integrated in the corresponding working areas, wherein the estimation formula of the sum of the effective doses of the corresponding nuclides to be integrated in different working areas is as follows:
；
wherein E is i The unit is mSv, which is the sum of the effective doses to be integrated of the nuclide i in different working areas; e (i) j For the effective dose to be accumulated of the nuclide i in the j-th working area, the unit is mSv, and j is an integer greater than 0;
step B233, estimating the irradiation dose in the individual according to the sum of the effective doses to be integrated of the corresponding nuclides in different working areas, wherein the estimation formula of the irradiation dose in the individual is as follows:
；
wherein E is Total (S) The dose of irradiation in the personnel of the staff is given in mSv; e (E) i The sum of the resulting to-be-integrated effective doses of the nuclide i in different working regions is given in mSv.
Optionally, in some embodiments of the present application, in the step B4, the post radiation dose includes an in-post irradiation dose, a post gamma dose, and a post neutron dose, where the post irradiation dose is a sum of personal irradiation doses of different employees corresponding to the post, the post gamma dose is a sum of personal gamma doses of different employees corresponding to the post, and the post neutron dose is a sum of personal neutron doses of different employees corresponding to the post.
Optionally, in some embodiments of the present application, in the step B5, the task radiation dose includes an intra-task radiation dose, a task γ dose, and a task neutron dose, where the intra-task radiation dose is a sum of intra-post radiation doses corresponding to different posts of the task, the task γ dose is a sum of post γ doses corresponding to different posts of the task, and the task neutron dose is a sum of post neutron doses corresponding to different posts of the task.
Optionally, in some embodiments of the present application, the step B6 includes:
performing risk assessment on the personal radiation dose according to the personal preset radiation dose to obtain a first risk assessment result;
performing risk assessment on the post radiation dose according to the post preset radiation dose to obtain a second risk assessment result;
performing risk assessment on the task radiation dose according to the task preset radiation dose to obtain a third risk assessment result;
and obtaining the nuclear-involved risk assessment result according to the first risk assessment result, the second risk assessment result and the third risk assessment result.
The application also provides a nuclear risk assessment system for implementing the nuclear risk assessment method, the nuclear risk assessment system comprises:
The acquisition module is used for acquiring detection data;
the personal radiation estimation module is used for estimating the personal radiation dose of staff according to the detection data;
the personal dose information recording module is used for updating the personal dose information file of the staff according to the personal radiation dose of the staff;
the post radiation estimation module is used for estimating post radiation doses corresponding to the posts according to the personal radiation doses of different staff at the same post;
the task radiation estimation module is used for estimating task radiation doses of corresponding tasks according to the post radiation doses of different posts of the same task; and
and the nuclear risk assessment module is used for carrying out nuclear risk assessment according to the personal radiation dose, the post radiation dose and the task radiation dose to obtain a nuclear risk assessment result.
The present application also provides a computer readable medium having stored thereon a computer program, characterized in that the program when processed and executed implements the above-mentioned nuclear risk assessment method.
According to the nuclear risk assessment method, system and computer readable medium, personal radiation dose, post radiation dose and task radiation dose can be estimated, personal dose information files of staff can be established, nuclear risk assessment can be carried out according to the personal radiation dose, post radiation dose and task radiation dose, multifunction is achieved, the use requirements of nuclear workers and other specific industries of enterprises such as nuclear power plants and nuclear element production and hospitals are met, the operation safety of the nuclear workers can be better assessed, and the life safety of the nuclear workers is guaranteed.
Drawings
In order to more clearly illustrate the technical solutions of the embodiments of the present application, the drawings that are needed in the description of the embodiments will be briefly introduced below, it being obvious that the drawings in the following description are only some embodiments of the present application, and that other drawings may be obtained according to these drawings without inventive effort for a person skilled in the art.
FIG. 1 is a schematic flow chart of a method for nuclear risk assessment provided herein;
FIG. 2 is a specific schematic flowchart of step B2 in a method for assessing nuclear risk provided in the present application;
FIG. 3 is a flowchart illustrating a step B21 in a method for assessing risk of nuclear involvement provided in the present application;
FIG. 4 is a flowchart of step B22 in a method for assessing risk of nuclear involvement provided in the present application;
FIG. 5 is a flowchart illustrating a step B23 in a method for assessing risk of nuclear involvement provided in the present application;
FIG. 6 is a first specific schematic flowchart of step B6 in a method for assessing nuclear risk provided in the present application;
FIG. 7 is a second specific schematic flowchart of step B6 in a method for nuclear risk assessment provided in the present application;
FIG. 8 is a schematic diagram of a nuclear risk assessment system provided herein;
FIG. 9 is a schematic diagram of a personal radiation estimation module of a nuclear risk assessment system provided herein;
FIG. 10 is a schematic diagram of a personal gamma dose estimation module of a nuclear risk assessment system provided herein;
FIG. 11 is a schematic diagram of a personal neutron dose estimation module of a nuclear risk assessment system provided herein;
FIG. 12 is a schematic diagram of an in-person exposure dose estimation module of a nuclear risk assessment system provided herein;
FIG. 13 is a first schematic diagram of a nuclear risk assessment module of a nuclear risk assessment system provided in the present application;
FIG. 14 is a second schematic diagram of a nuclear risk assessment module of a nuclear risk assessment system provided herein;
reference numerals illustrate:
100-acquisition module, 200-personal radiation estimation module, 210-personal gamma dose estimation module, 211-first gamma dose sub-estimation module, 212-second gamma dose sub-estimation module, 220-personal neutron dose estimation module, 221-first neutron dose sub-estimation module, 222-second neutron dose quantum estimation module, 230-personal internal radiation dose estimation module, 231-first internal radiation dose estimation module, 232-second internal radiation dose estimation module, 233-third internal radiation dose estimation module, 240-personal dose estimation module, 300-personal dose information recording module, 400-post radiation estimation module, 500-task radiation estimation module, 600-nuclear risk estimation module, 610-first risk estimation module, 620-second risk estimation module, 630-third risk estimation module, 640-fourth risk estimation module, 650-risk estimation generation module.
Description of the embodiments
Embodiments of the present invention are described in detail below, examples of which are illustrated in the accompanying drawings, wherein like or similar reference numerals refer to like or similar elements or elements having like or similar functions throughout. The embodiments described below by referring to the drawings are illustrative only and are not to be construed as limiting the invention.
As used herein, the singular forms "a", "an", "the" and "the" are intended to include the plural forms as well, unless expressly stated otherwise, as understood by those skilled in the art. It will be further understood that the terms "comprises" and/or "comprising," when used in this specification, specify the presence of stated features, integers, steps, operations, but do not preclude the presence or addition of one or more other features, integers, steps, operations.
It will be understood by those skilled in the art that all terms (including technical and scientific terms) used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this invention belongs unless defined otherwise. It will be further understood that terms, such as those defined in commonly used dictionaries, should be interpreted as having a meaning that is consistent with their meaning in the context of the prior art and will not be interpreted in an idealized or overly formal sense unless expressly so defined herein.
It will be appreciated by those skilled in the art that references to "application," "application program," "application software," and similar concepts herein are intended to be equivalent concepts well known to those skilled in the art, and refer to computer software, organically constructed from a series of computer instructions and related data resources, suitable for electronic execution. Unless specifically specified, such naming is not limited by the type, level of programming language, nor by the operating system or platform on which it operates. Of course, such concepts are not limited by any form of terminal.
The application provides a nuclear risk assessment method, please refer to fig. 1, and fig. 1 shows a schematic flowchart of the nuclear risk assessment method provided by the application. As shown in fig. 1, the method for assessing a nuclear risk may include the following steps:
and B1, acquiring detection data.
The detection data can be obtained by detecting the actual measured value by adopting the metering detection equipment on site, and then the staff inputs the detection data in the back-end equipment, and of course, the detection data can also be directly input into the back-end equipment by the metering detection equipment.
In step B1, the detection data may include, but is not limited to, work The activity of the punctiform source of the area, the distance of the working area from the punctiform source, the measurement at the top of the head of the working area 24 The Na gamma initial count rate, the residence time of the working area, the air activity concentration of the nuclide in the working area and the like are obtained so as to facilitate the subsequent estimation of the personal radiation dose.
In some embodiments of the present application, the entire workplace may be considered as a working area, and only detection data of one working area need be acquired at this time.
In other embodiments of the present application, if the occupation area of the workplace is larger, the deviation of the detection results performed by the metering detection device at different positions is larger, in order to ensure the estimation accuracy, the whole workplace may be divided into at least two working areas, at this time, detection data of the at least two working areas need to be acquired, and the estimation accuracy is higher by acquiring the detection data of the different working areas, so that the subsequent estimation of the personal radiation dose for the different working areas respectively.
And step B2, estimating personal radiation dose of staff according to the detection data.
The radiation dose generally includes two types, i.e., an inner radiation dose and an outer radiation dose, which are difficult to calculate in the same estimation manner, so that the present embodiment provides a high-precision estimation manner to better ensure the estimation accuracy in order to ensure the estimation accuracy.
In order to provide the estimation accuracy of the radiation dose, the embodiment respectively carries out the estimation of the internal radiation dose and the estimation of the external radiation dose, combines the estimation of the external radiation dose and the estimation of the internal radiation dose, can obtain the estimation value of the personal radiation dose, can better protect the professional radiation safety and health of nuclear staff in China, and contributes to the radiation protection industry in China. The specific process is as follows:
specifically, step B2 specifically includes steps B21 to B24. As shown in fig. 2, fig. 2 shows a specific schematic flowchart of step B2 in a method for assessing a nuclear risk provided in the present application.
And step B21, estimating personal gamma dosage of staff according to the activity of the point-shaped source in the working area, the distance between the working area and the point-shaped source and the residence time of the working area.
Step B22, according to measurements at the overhead of the working area 24 Na gamma initial count rate, the individual neutron dose was estimated.
And step B23, estimating the irradiation dose in the individual according to the residence time of the working area and the air activity concentration of different nuclides.
And step B24, obtaining personal radiation dose of staff according to the personal gamma dose, the personal neutron dose and the personal internal radiation dose. In the embodiment of the application, the personal gamma dose and the personal neutron dose are the external irradiation dose, the gamma radiation dose and the neutron radiation dose are estimated separately, and the estimated gamma radiation dose and the estimated neutron radiation dose are combined to obtain the estimated value of the external irradiation dose. And then combining the external irradiation dose with the internal irradiation dose to obtain an estimated value of the personal irradiation dose.
Specifically, step B21 specifically includes steps B211 to B212. As shown in fig. 3, fig. 3 shows a specific schematic flowchart of step B21 in a method for assessing a nuclear risk provided in the present application.
And step B211, estimating gamma doses of staff in different working areas according to the activity of the point-like source in the working area, the distance between the working area and the point-like source and the residence time of the working area.
The gamma dose rate of different working areas is estimated by the activity of the point-shaped source of the working area and the distance between the working area and the point-shaped source, and the estimation formula of the gamma dose rate of different working areas is as follows:
(1)
wherein P is γj The gamma dose rate of the j-th working area is Gy/h, and j is an integer greater than 0; q (Q) j The unit is Bq for the point source activity of the j-th working area; Γ is a constant 3.42×10 -13 The unit is Gy.m 2 /(h·Bq)；R j Distance from the point source to the jth working area, singlyThe bit is m.
The gamma dose of staff in different working areas is estimated through the gamma dose rate and the residence time of the working areas, and an estimation formula of the gamma dose in different working areas is as follows:
(2)
wherein X is j Gamma dose for the j-th working area, the unit is Gy, j is an integer greater than 0; p (P) γj The gamma dose rate of the jth working area is shown as Gy/h; t (T) j The residence time in h is the j-th working area.
Combining formula (1) and formula (2) can give formula (3):
(3)
wherein X is j Gamma dose for the j-th working area, the unit is Gy, j is an integer greater than 0; q (Q) j The unit is Bq for the point source activity of the j-th working area; Γ is a constant 3.42×10 -13 The unit is Gy.m 2 /(h·Bq)；T j The residence time of the jth working area is given in h; r is R j The j-th working area is a distance from the point source in m.
Illustratively, when the entire workplace is considered as 1 work area, j is 1 and the estimation process of step B211 is as follows:
wherein X is 1 Gamma dose for the 1 st working area in Gy; q (Q) 1 The unit is Bq, which is the activity of the point source in the 1 st working area; Γ is a constant 3.42×10 -13 The unit is Gy.m 2 /(h·Bq)；T 1 The residence time for the 1 st working area is given in h; r is R 1 The distance from the point source to the 1 st working area is given in m.
Illustratively, when the entire workplace is divided into 2 work areas, j has values of 1 and 2, and the estimation process of step B211 is as follows:
wherein X is 1 And X 2 Gamma doses of the 1 st and 2 nd working areas respectively, the unit is Gy; q (Q) 1 And Q 2 The point source activities of the 1 st and 2 nd working areas are respectively expressed as Bq; Γ is a constant 3.42×10 -13 The unit is Gy.m 2 /(h·Bq)；T 1 And T 2 The residence time of the 1 st working area and the 2 nd working area is h; r is R 1 And R is 2 The distance between the 1 st and 2 nd working areas and the point source is m.
Step B212, estimating personal gamma dose of staff according to gamma dose of staff in different working areas, wherein an estimation formula of the personal gamma dose is as follows:
(4)
wherein X is Total (S) Personal gamma dose for staff, in Gy; x is X j The gamma dose for the j-th working region, j being an integer greater than 0.
Illustratively, when the entire workplace is considered as 1 work area, j is 1 and the estimation process of step B212 is as follows:
wherein X is Total (S) Personal gamma dose for staff, in Gy; x is X 1 Gamma dose for the 1 st working area.
Illustratively, when the entire workplace is divided into 2 work areas, j has values of 1 and 2, and the estimation process of step B212 is as follows:
wherein X is Total (S) Personal gamma dose for staff, in Gy; x is X 1 And X 2 Gamma doses for the 1 st and 2 nd working areas, respectively.
Specifically, step B22 specifically includes steps B221 to B222. As shown in fig. 4, fig. 4 is a specific schematic flowchart of step B22 in a method for assessing a nuclear risk provided in the present application.
Step B221, measured from the overhead of the work area 24 The initial counting rate of Na gamma is used for estimating neutron dose of staff in different working areas, and an estimation formula of the neutron dose of the staff in the different working areas is as follows:
(5)
wherein,,neutron dose of staff in a j-th working area is given in Gy, and j is an integer larger than 0; f (f) j Is the coefficient related to the irradiation and measurement time in the jth working area, and is expressed as s -1 ；D Fj The unit of the absorption dose generated for the unit neutron fluence of the jth working area is Gy cm 2 Neutrons; n (t) 0 ) j Measured at the top of the head for the jth working area 24 Na gamma initial count rate in neutron s/cm 2 。
Specifically, f j The calculation formula of (2) is as follows:
(6)
wherein f j Is the illumination and measurement time dependent coefficient in the jth working area,in s -1 The method comprises the steps of carrying out a first treatment on the surface of the Lambda is 24 Decay constant of Na in s -1 ；T Measuring For sustained exposure time, the unit is s; t is t s For the time interval from the end of the illumination to the beginning of the measurement, the unit is s; t is the measurement time in s. From this, f j Is calculated.
In this embodiment, the detection data in step B1 includes a coefficient f related to the irradiation and measurement time in the jth working area j And an absorbed dose D generated by unit neutron fluence in the jth working area Fj 。
Illustratively, when the entire workplace is considered as 1 work area, j is 1 and the estimation process of step B221 is as follows:
wherein,,neutron dose of staff in the 1 st working area is given in Gy; f (f) 1 Is the coefficient related to the irradiation and measurement time in the 1 st working area, and the unit is s -1 ；D F1 The absorption dose generated for the unit neutron fluence of the 1 st working area is expressed in Gy cm 2 Neutrons; n (t) 0 ) 1 Measured at the top of the head for work area 1 24 Na gamma initial count rate in neutron s/cm 2 。
Illustratively, when the entire workplace is considered as 2 work areas, j has values of 1 and 2, and the estimation process of step B221 is as follows:
wherein,,and->Neutron doses of staff in the 1 st working area and the 2 nd working area are respectively shown in Gy; f (f) 1 And f 2 The irradiation and measurement time related coefficients in the 1 st and 2 nd working areas are respectively expressed as s -1 ；D F1 And D F2 Absorbed dose generated by neutron fluence of 1 st and 2 nd working areas respectively, and the unit is Gy cm 2 Neutrons; n (t) 0 ) 1 And n (t) 0 ) 2 Measured at the top of the head for the 1 st and 2 nd working areas, respectively 24 Na gamma initial count rate in neutron s/cm 2 。
Step B222, estimating personal neutron dose of staff according to neutron dose of staff in different working areas, wherein an estimation formula of the personal neutron dose is as follows:
(7)
wherein,,personal neutron dose for staff, in Gy; />Neutron dose of staff in the j-th working area is given in Gy, and j is an integer greater than 0.
Illustratively, when the entire workplace is considered as 1 work area, j is 1 and the estimation process of step B222 is as follows:
wherein,,personal neutron for staffThe amount, in Gy; />Neutron dose for staff in work area 1 in Gy units.
Illustratively, when the entire workplace is divided into 2 work areas, j has values of 1 and 2, and the estimation process of step B222 is as follows:
wherein,,personal neutron dose for staff, in Gy; />And->Neutron doses of staff in the 1 st and 2 nd working areas are shown in Gy.
Specifically, step B23 specifically includes steps B231 to B233. As shown in fig. 5, fig. 5 shows a specific schematic flowchart of step B23 in a method for assessing a nuclear risk provided in the present application.
And step B231, estimating the effective dose of the corresponding nuclide to be accumulated in the corresponding working area according to the residence time of the working area and the air activity concentration of the nuclide.
The intake of the corresponding nuclide in the corresponding working area is estimated by the residence time of the working area and the air activity concentration of the nuclide, and an estimation formula of the intake of the corresponding nuclide is as follows:
(8)
wherein I is ij For the uptake of nuclide i in the jth working region, the unit is Bq, j is an integer greater than 0; c (C) ij Air activity at the jth working region for nuclide iConcentration in Bq/m 3 The method comprises the steps of carrying out a first treatment on the surface of the B is the respiration rate of the person, and the unit is m 3 /h；T j The unit of the residence time of the staff in the j-th working area is h.
The effective dose of the corresponding nuclide to be integrated in the corresponding working area is estimated through the intake of the corresponding nuclide, and an estimation formula of the effective dose of the corresponding nuclide to be integrated in the corresponding working area is as follows:
(9)
wherein E (i) j For the effective dose to be accumulated of the nuclide i in the j-th working area, the unit is mSv, and j is an integer greater than 0; i ij For the uptake of nuclide i in the jth working region, the unit is Bq; e, e i The dose conversion coefficient for nuclide i is given in mSv/Bq.
Combining formula (8) and formula (9) can give formula (10):
(10)
wherein E (i) j For the effective dose to be accumulated of the nuclide i in the j-th working area, the unit is mSv, and j is an integer greater than 0; c (C) ij The air activity concentration of the nuclide i in the jth working area is expressed as Bq/m 3 The method comprises the steps of carrying out a first treatment on the surface of the B is the respiration rate of the person, and the unit is m 3 /h；T j The stay time of the staff in the j-th working area is h; e, e i The dose conversion coefficient for nuclide i is given in mSv/Bq. In this embodiment, i=radon, uranium, plutonium, tritium, and the like.
Illustratively, when the entire workplace is considered as 1 working area, j is 1, and the estimation process of the resulting to-be-integrated effective dose of radon in the corresponding working area in step B231 is as follows:
wherein E (radon) 1 Is the effective dose of radon in the 1 st working area to be accumulated, and the unit is mSv; c (C) Radon 1 The air activity concentration of radon in the 1 st working area is Bq/m 3 The method comprises the steps of carrying out a first treatment on the surface of the B is the respiration rate of the person, and the unit is m 3 /h；T 1 The residence time of staff in the 1 st working area is h; e, e Radon Is the dose conversion coefficient of radon, and has the unit of mSv/Bq. Similarly, the effective dose to be accumulated of other nuclides (uranium, plutonium, tritium, etc.) in the corresponding working areas is estimated based on the formula (10), and the detailed description is omitted.
Illustratively, when the entire workplace is divided into 2 working areas, j has values of 1 and 2, and the estimation process of the effective dose of radon to be accumulated in the corresponding working area in step B231 is as follows:
Wherein E (radon) 1 And E (radon) 2 The unit is mSv, which is the effective dose of radon in the 1 st and 2 nd working areas; c (C) Radon 1 And C Radon 2 The air activity concentration of radon in the 1 st and 2 nd working areas is Bq/m 3 The method comprises the steps of carrying out a first treatment on the surface of the B is the respiration rate of the person, and the unit is m 3 /h；T 1 And T 2 The stay time of the staff in the 1 st working area and the 2 nd working area is h; e, e Radon Is the dose conversion coefficient of radon, and has the unit of mSv/Bq. Similarly, the effective dose to be accumulated of other nuclides (uranium, plutonium, tritium, etc.) in the corresponding working areas is estimated based on the formula (10), and the detailed description is omitted.
Step B232, estimating the sum of the effective doses of the corresponding nuclides to be integrated in different working areas according to the effective doses of the corresponding nuclides to be integrated in the corresponding working areas, wherein the estimation formula of the sum of the effective doses of the corresponding nuclides to be integrated in different working areas is as follows:
(11)
wherein E is i The unit is mSv, which is the sum of the effective doses to be integrated of the nuclide i in different working areas; e (i) j For the resulting to-be-integrated effective dose of nuclide i in the jth working region, the unit is mSv, and j is an integer greater than 0.
Illustratively, when the entire workplace is considered as 1 working area, j is 1, and the estimation process of the sum of the resulting to-be-integrated effective doses of radon in the different working areas in step B232 is as follows:
Wherein E is Radon The unit is mSv which is the sum of the effective doses to be accumulated of radon in different working areas; e (radon) 1 Is the effective dose of radon in the 1 st working area, and the unit is mSv. Similarly, the sum of the effective doses to be accumulated of other nuclides (uranium, plutonium, tritium, etc.) in different working areas is estimated based on the formula (11), and the description thereof is not repeated here.
Illustratively, when the entire workplace is divided into 2 working areas, j has values of 1 and 2, and the estimation process of the sum of the resulting to-be-integrated effective doses of radon in the different working areas in step B232 is as follows:
wherein E is Radon The unit is mSv which is the sum of the effective doses to be accumulated of radon in different working areas; e (radon) 1 And E (radon) 2 The unit is mSv, which is the effective dose of radon in the 1 st and 2 nd working areas. Similarly, the sum of the effective doses to be accumulated of other nuclides (uranium, plutonium, tritium, etc.) in different working areas is estimated based on the formula (11), and the description thereof is not repeated here.
Step B233, estimating the irradiation dose in the individual according to the sum of the effective doses to be integrated of the corresponding nuclides in different working areas, wherein the estimation formula of the irradiation dose in the individual is as follows:
(12)
Wherein E is Total (S) The dose of irradiation in the personnel of the staff is given in mSv; e (E) i The sum of the resulting to-be-integrated effective doses of the nuclide i in different working regions is given in mSv.
Illustratively, where the nuclides include radon, uranium, plutonium, and tritium, the estimation of the dose of radiation in the individual in step B233 is given by the following formula:
wherein E is Total (S) The dose of irradiation in the personnel of the staff is given in mSv; e (E) Radon The unit is mSv which is the sum of the effective doses to be accumulated of radon in different working areas; e (E) Uranium (uranium) The unit is mSv which is the sum of the effective doses to be accumulated of uranium in different working areas; e (E) Plutonium (Pythium) The unit is mSv which is the sum of the effective doses to be accumulated of plutonium in different working areas; e (E) Tritium Is the sum of the resulting to-be-integrated effective doses of tritium in different working areas, and is expressed as mSv.
And step B3, updating the personal dose information file of the staff according to the personal radiation dose of the staff.
The personal dose information file is recorded with personal dose information of staff, the personal dose information comprises historical radiation doses and accumulated radiation doses of the staff, and after the personal radiation doses of the staff are estimated, the personal radiation doses of the staff and the historical radiation doses of the staff are added to obtain the accumulated radiation doses of the staff.
And step B4, estimating the post radiation dose of the corresponding post according to the personal radiation doses of different staff at the same post.
Each task typically includes a different post, each requiring one or more employees, in performing the relevant task.
For example, assuming that two vehicles are required to perform a transportation mission, each vehicle is equipped with a commander, a driver, and a charger, the transportation mission involves three stations, namely a command station, a driving station, and a charging station, wherein the command station includes two commanders, the driving station includes two drivers, and the charging station includes two loaders. Then, the post radiation dose of the command post is the sum of the personal radiation doses of the two directors, the post radiation dose of the driving post is the sum of the personal radiation doses of the two drivers, and the post radiation dose of the charging post is the sum of the personal radiation doses of the two loaders.
In this embodiment, the post radiation dose includes an in-post radiation dose, a post gamma dose, and a post neutron dose, where the post radiation dose is a sum of the in-person radiation doses of different employees corresponding to the post, the post gamma dose is a sum of the personal gamma doses of different employees corresponding to the post, and the post neutron dose is a sum of the personal neutron doses of different employees corresponding to the post. For example, the post internal irradiation dose of the command post is the sum of the personal internal irradiation doses of two command persons, the post gamma dose of the driving post is the sum of the personal gamma doses of two drivers, and the post neutron dose of the charging post is the sum of the personal neutron doses of two charging persons.
And step B5, estimating the task radiation dose of the corresponding task according to the post radiation doses of different posts of the same task.
The transportation tasks comprise a command post, a driving post and a charging post, and the task radiation dose of the transportation tasks is the sum of the post radiation dose of the command post, the post radiation dose of the driving post and the post radiation dose of the charging post.
In this embodiment, the task radiation dose includes an intra-task radiation dose, a task gamma dose, and a task neutron dose, where the intra-task radiation dose is a sum of intra-post radiation doses corresponding to different posts of the task, the task gamma dose is a sum of post gamma doses corresponding to different posts of the task, and the task neutron dose is a sum of post neutron doses corresponding to different posts of the task. For example, the in-job irradiation dose of the transport job is the sum of the in-job irradiation dose of the command post, the in-job irradiation dose of the drive post, and the in-job irradiation dose of the charge post, the in-job gamma dose of the transport job is the sum of the in-job gamma dose of the command post, the in-job gamma dose of the drive post, and the in-job gamma dose of the charge post, and the in-job neutron dose of the transport job is the sum of the in-job neutron dose of the command post, the in-job neutron dose of the drive post, and the in-job neutron dose of the charge post.
And step B6, performing nuclear risk assessment according to the personal radiation dose, the post radiation dose and the task radiation dose to obtain a nuclear risk assessment result.
In some embodiments of the present application, step B6 specifically includes steps B61 to B64. As shown in fig. 6, fig. 6 shows a first specific schematic flowchart of step B6 in a method for assessing a nuclear risk provided in the present application.
And step B61, performing risk assessment on the personal radiation dose according to the personal preset radiation dose to obtain a first risk assessment result.
In step B61, it is determined whether the personal radiation dose meets the standard by comparing the personal radiation dose with the personal preset radiation dose. If the personal radiation dose is larger than the personal preset radiation dose, the first risk assessment result is high risk; if the personal radiation dose is less than or equal to the personal preset radiation dose, the first risk assessment result is a low risk. In this embodiment, the personal preset radiation dose may be determined according to a historical actual monitoring value, for example, when performing risk assessment on the personal radiation dose of the driver of the transportation task, the actual radiation monitoring value of the driver of the previous transportation task may be regarded as the personal preset radiation dose for this assessment.
And step B62, performing risk assessment on the post radiation dose according to the post preset radiation dose, and obtaining a second risk assessment result.
In step B62, it is determined whether the post radiation dose meets the standard by comparing the post radiation dose with the post preset radiation dose. If the post radiation dose is larger than the post preset radiation dose, the second risk assessment result is a high risk; and if the post radiation dose is smaller than or equal to the post preset radiation dose, the second risk assessment result is a low risk. In this embodiment, the post preset radiation dose may be determined according to a historical actual monitoring value, for example, when performing risk assessment on the post radiation dose of the driving post of the transportation task, the sum of actual radiation monitoring values of all staff of the driving post of the previous transportation task may be regarded as the post preset radiation dose for this assessment.
And step B63, performing risk assessment on the task radiation dose according to the task preset radiation dose, and obtaining a third risk assessment result.
In step B63, the task radiation dose is compared with the task preset radiation dose, so as to determine whether the task radiation dose meets the standard. If the task radiation dose is larger than the task preset radiation dose, the third risk assessment result is a high risk; if the task radiation dose is smaller than or equal to the task preset radiation dose, the third risk assessment result is low risk. In this embodiment, the task radiation dose may be determined according to a historical actual monitoring value, for example, when performing risk assessment on the task radiation dose of the transportation task, the sum of actual radiation monitoring values of all staff members under the previous transportation task may be regarded as the task preset radiation dose for this assessment.
And step B64, obtaining a nuclear-involved risk assessment result according to the first risk assessment result, the second risk assessment result and the third risk assessment result.
In step B64, if the first risk assessment result, the second risk assessment result, and the third risk assessment result are all low risk, the verification-related risk assessment result is low risk; if at least one of the first risk assessment result, the second risk assessment result and the third risk assessment result is a high risk, the nuclear-involved risk assessment result is a high risk.
In other embodiments of the present application, step B6 specifically includes steps B65 to B69. As shown in fig. 7, fig. 7 shows a second specific schematic flowchart of step B6 in a method for assessing a nuclear risk provided in the present application.
And step B65, performing risk assessment on the personal radiation dose according to the personal preset radiation dose to obtain a first risk assessment result.
In step B65, it is determined whether the personal radiation dose meets the standard by comparing the personal radiation dose with the personal preset radiation dose. If the personal radiation dose is larger than the personal preset radiation dose, the first risk assessment result is high risk; if the personal radiation dose is less than or equal to the personal preset radiation dose, the first risk assessment result is a low risk. In this embodiment, the personal preset radiation dose may be determined according to a historical actual monitoring value, for example, when performing risk assessment on the personal radiation dose of the driver of the transportation task, the actual radiation monitoring value of the driver of the previous transportation task may be regarded as the personal preset radiation dose for this assessment.
And step B66, performing risk assessment on the post radiation dose according to the post preset radiation dose, and obtaining a second risk assessment result.
In step B66, it is determined whether the post radiation dose meets the standard by comparing the post radiation dose with the post preset radiation dose. If the post radiation dose is larger than the post preset radiation dose, the second risk assessment result is a high risk; and if the post radiation dose is smaller than or equal to the post preset radiation dose, the second risk assessment result is a low risk. In this embodiment, the post preset radiation dose may be determined according to a historical actual monitoring value, for example, when performing risk assessment on the post radiation dose of the driving post of the transportation task, the sum of actual radiation monitoring values of all staff of the driving post of the previous transportation task may be regarded as the post preset radiation dose for this assessment.
And B67, performing risk assessment on the task radiation dose according to the task preset radiation dose, and obtaining a third risk assessment result.
In step B67, the task radiation dose is compared with the task preset radiation dose, so as to determine whether the task radiation dose meets the standard. If the task radiation dose is larger than the task preset radiation dose, the third risk assessment result is a high risk; if the task radiation dose is smaller than or equal to the task preset radiation dose, the third risk assessment result is low risk. In this embodiment, the task radiation dose may be determined according to a historical actual monitoring value, for example, when performing risk assessment on the task radiation dose of the transportation task, the sum of actual radiation monitoring values of all staff members under the previous transportation task may be regarded as the task preset radiation dose for this assessment.
And step B68, performing risk assessment on the personal dose information according to the personal dose information to obtain a fourth risk assessment result.
In step B68, the personal dose information includes an accumulated radiation dose, where the accumulated radiation dose is a sum of the personal radiation dose of the employee in the evaluation and the historical radiation dose of the employee, and if the accumulated radiation dose is greater than the accumulated preset dose, the fourth risk evaluation result is a high risk; if the accumulated radiation dose is less than or equal to the accumulated preset dose, the fourth risk assessment result is a low risk.
And step B69, obtaining a nuclear-involved risk assessment result according to the first risk assessment result, the second risk assessment result, the third risk assessment result and the fourth risk assessment result.
In step B64, if the first risk assessment result, the second risk assessment result, the third risk assessment result, and the fourth risk assessment result are all low risk, the verification-related risk assessment result is low risk; if at least one of the first risk assessment result, the second risk assessment result, the third risk assessment result and the fourth risk assessment result is a high risk, the verification-related risk assessment result is a high risk.
Referring to fig. 8, the present application further provides a nuclear risk assessment system, which is configured to implement the nuclear risk assessment method, where the nuclear risk assessment system includes an obtaining module 100, a personal radiation estimation module 200, a personal dose information recording module 300, a post radiation estimation module 400, a task radiation estimation module 500, and a nuclear risk assessment module 600. The acquisition module 100 is used for acquiring detection data; the personal radiation estimation module 200 is configured to estimate a personal radiation dose of the employee according to the detection data; the personal dose information recording module 300 is used for updating the personal dose information file of the staff according to the personal radiation dose of the staff; the post radiation estimation module 400 is configured to estimate post radiation doses corresponding to the same post according to personal radiation doses of different employees at the same post; the task radiation estimation module 500 is configured to estimate task radiation doses of corresponding tasks according to post radiation doses of different posts of the same task; the nuclear risk assessment module 600 is configured to perform nuclear risk assessment according to the personal radiation dose, the post radiation dose, and the task radiation dose, and obtain a nuclear risk assessment result.
Specifically, as shown in fig. 9, the personal radiation estimation module includes a personal gamma dose estimation module 210, a personal neutron dose estimation module 220, an intra-personal radiation dose estimation module 230, and a personal dose estimation module 140.
The personal gamma dose estimation module 210 is configured to estimate a personal gamma dose of the employee based on the activity of the punctual source in the work area, the distance of the work area from the punctual source, and the residence time of the work area.
The personal neutron dose estimation module 220 is used for measuring according to the overhead of the working area 24 Na gamma initial count rate, the individual neutron dose was estimated.
The in-person exposure dose estimation module 230 is configured to estimate an in-person exposure dose based on the residence time of the work area and the air activity concentration of the different species.
The personal dose estimation module 240 is configured to obtain a personal radiation dose of the employee based on the personal gamma dose, the personal neutron dose, and the personal internal radiation dose.
Specifically, as shown in fig. 10, the personal gamma dose estimation module 210 includes a first gamma dose sub-estimation module 211 and a second gamma dose sub-estimation module 212.
The first gamma dose sub-estimation module 211 is configured to estimate gamma doses of staff in different working areas according to the activity of the punctiform source in the working area, the distance between the working area and the punctiform source, and the residence time of the working area, where the calculation formula of the gamma doses of staff in different working areas is:
Wherein X is j Gamma dose for the j-th working area, the unit is Gy, j is an integer greater than 0; q (Q) j The unit is Bq for the point source activity of the j-th working area; Γ is a constant 3.42×10 -13 The unit is Gy.m 2 /(h·Bq)；T j The residence time of the jth working area is given in h; r is R j The j-th working area is a distance from the point source in m.
The second gamma dose sub-estimation module 212 is configured to estimate a personal gamma dose of the employee according to the gamma dose of the employee in different working areas, where the estimated formula of the personal gamma dose is:
wherein X is Total (S) Personal gamma dose for staff, in Gy; x is X j The gamma dose for the j-th working region, j being an integer greater than 0.
Specifically, as shown in fig. 11, the personal neutron dose estimation module 220 includes a first neutron agent quantum estimation module 221 and a second neutron agent quantum estimation module 222.
The first neutron agent quantum estimation module 221 is for measuring from the overhead of the working area 24 The initial counting rate of Na gamma is used for estimating neutron dose of staff in different working areas, and an estimation formula of the neutron dose of the staff in the different working areas is as follows:
wherein,,neutron dose of staff in a j-th working area is given in Gy, and j is an integer larger than 0; f (f) j Is the coefficient related to the irradiation and measurement time in the jth working area, and is expressed as s -1 ；D Fj The unit of the absorption dose generated for the unit neutron fluence of the jth working area is Gy cm 2 Neutrons; n (t) 0 ) j Measured at the top of the head for the jth working area 24 Na gamma initial count rate in neutron s/cm 2 。
The second neutron agent quantum estimation module 222 is configured to estimate a personal neutron dose of the staff according to neutron doses of the staff in different working areas, where an estimation formula of the personal neutron dose is as follows:
wherein,,personal neutron dose for staff, in Gy; />Neutron dose of staff in the j-th working area is given in Gy, and j is an integer greater than 0.
Specifically, as shown in fig. 12, the in-person irradiation dose estimation module 230 includes a first internal irradiation dose estimation module 231, a second internal irradiation dose estimation module 232, and a third internal irradiation dose estimation module 233.
The first internal irradiator quantum estimation module 231 is configured to estimate an effective dose to be accumulated of the corresponding nuclide in the corresponding working area according to the residence time of the working area and the air activity concentration of the nuclide, and an estimation formula of the effective dose to be accumulated of the corresponding nuclide in the corresponding working area is as follows:
Wherein E (i) j For the effective dose to be accumulated of the nuclide i in the j-th working area, the unit is mSv, and j is an integer greater than 0; c (C) ij The air activity concentration of the nuclide i in the jth working area is expressed as Bq/m 3 The method comprises the steps of carrying out a first treatment on the surface of the B is the respiration rate of the person in units ofm 3 /h；T j The stay time of the staff in the j-th working area is h; e, e i The dose conversion coefficient for nuclide i is given in mSv/Bq. In this embodiment, i=radon, uranium, plutonium, tritium, and the like.
The second internal irradiator quantum estimation module 232 is configured to estimate a sum of the effective doses of the corresponding nuclides to be accumulated in the different working areas according to the effective doses of the corresponding nuclides to be accumulated in the corresponding working areas, where an estimation formula of the sum of the effective doses of the corresponding nuclides to be accumulated in the different working areas is:
wherein E is i The unit is mSv, which is the sum of the effective doses to be integrated of the nuclide i in different working areas; e (i) j For the resulting to-be-integrated effective dose of nuclide i in the jth working region, the unit is mSv, and j is an integer greater than 0.
The third internal irradiator quantum estimation module 233 is configured to estimate an internal individual irradiator dose according to a sum of the effective doses to be integrated of the corresponding nuclides in different working areas, where an estimation formula of the internal individual irradiator dose is:
/>
Wherein E is Total (S) The dose of irradiation in the personnel of the staff is given in mSv; e (E) i The sum of the resulting to-be-integrated effective doses of the nuclide i in different working regions is given in mSv.
In some embodiments of the present application, as shown in fig. 13, the core-related risk assessment module 600 includes a first risk assessment module 610, a second risk assessment module 620, a third risk assessment module 630, and a risk assessment generation module 650. The first risk assessment module 610 is configured to perform risk assessment on the personal radiation dose according to the personal preset radiation dose, so as to obtain a first risk assessment result. The second risk assessment module 620 is configured to perform risk assessment on the post radiation dose according to the post preset radiation dose, to obtain a second risk assessment result. The third risk assessment module 630 is configured to perform risk assessment on the task radiation dose according to the task preset radiation dose, so as to obtain a third risk assessment result. The risk assessment generating module 650 is configured to obtain a verification risk assessment result according to the first risk assessment result, the second risk assessment result, and the third risk assessment result.
In other embodiments of the present application, as shown in fig. 14, the core-related risk assessment module 600 includes a first risk assessment module 610, a second risk assessment module 620, a third risk assessment module 630, a fourth risk assessment module 640, and a risk assessment generation module 650. The first risk assessment module 610 is configured to perform risk assessment on the personal radiation dose according to the personal preset radiation dose, so as to obtain a first risk assessment result. The second risk assessment module 620 is configured to perform risk assessment on the post radiation dose according to the post preset radiation dose, to obtain a second risk assessment result. The third risk assessment module 630 is configured to perform risk assessment on the task radiation dose according to the task preset radiation dose, so as to obtain a third risk assessment result. The fourth risk assessment module 640 is configured to perform risk assessment on the personal dose information according to the personal dose information, to obtain a fourth risk assessment result. The risk assessment generating module 650 is configured to obtain a risk assessment result related to the core according to the first risk assessment result, the second risk assessment result, the third risk assessment result, and the fourth risk assessment result.
Those of ordinary skill in the art will appreciate that all or a portion of the steps of the various methods of the above embodiments may be performed by instructions, or by instructions controlling associated hardware, which may be stored in a computer-readable storage medium and loaded and executed by a processor.
To this end, embodiments of the present application provide a computer readable storage medium having stored therein a computer program that is capable of being loaded by a processor to perform the steps of any of the nuclear risk assessment methods provided by embodiments of the present application. For example, the computer program may perform the steps of:
step B1, obtaining detection data;
step B2, estimating personal radiation dose of staff according to the detection data;
step B3, updating personal dose information files of staff according to personal radiation doses of the staff;
step B4, estimating post radiation doses corresponding to the posts according to the personal radiation doses of different staff at the same post;
step B5, estimating task radiation doses of corresponding tasks according to the post radiation doses of different posts of the same task;
and step B6, performing nuclear risk assessment according to the personal radiation dose, the post radiation dose and the task radiation dose to obtain a nuclear risk assessment result.
The specific implementation of each operation above may be referred to the previous embodiments, and will not be described herein.
Wherein the computer-readable storage medium may comprise: read Only Memory (ROM), random access Memory (RAM, random Access Memory), magnetic or optical disk, and the like.
Because the computer program stored in the computer readable storage medium may execute the steps in any of the methods for risk assessment of nuclear involvement provided in the embodiments of the present application, the beneficial effects that any of the methods for risk assessment of nuclear involvement provided in the embodiments of the present application may be achieved, which are detailed in the previous embodiments and are not described herein.
The above detailed description of a method, a system and a computer readable medium for assessing risk of nuclear risk provided in the embodiments of the present application, the specific examples are applied herein to illustrate the principles and embodiments of the present application, and the above description of the embodiments is only used to help understand the method and core idea of the present application; meanwhile, those skilled in the art will have variations in the specific embodiments and application scope in light of the ideas of the present application, and the present description should not be construed as limiting the present application in view of the above.
Claims (9)
1. A method for nuclear risk assessment, comprising:
step B1, obtaining detection data;
step B2, estimating personal radiation dose of staff according to the detection data;
step B3, updating personal dose information files of staff according to the personal radiation doses of the staff;
step B4, estimating post radiation doses of corresponding posts according to the personal radiation doses of different staff at the same post;
step B5, estimating task radiation doses of corresponding tasks according to the post radiation doses of different posts of the same task; and
step B6, performing nuclear risk assessment according to the personal radiation dose, the post radiation dose and the task radiation dose to obtain a nuclear risk assessment result;
in the step B1, the detection data comprise the activity of the point source of the working area, the distance of the working area from the point source, and the measurement at the top of the head of the working area 24 Na gamma initial count rate, residence time of the working area, and air activity concentration of the nuclide of the working area;
the step B2 comprises the following steps:
step B21, estimating personal gamma dosage of staff according to activity of the point-shaped source of the working area, distance between the working area and the point-shaped source and residence time of the working area;
Step B22, according to measurements at the overhead of the working area 24 Na gamma initial count rate, estimated individual neutron dose;
step B23, estimating the irradiation dose in the individual according to the residence time of the working area and the air activity concentration of different nuclides;
and step B24, obtaining personal radiation dose of the staff according to the personal gamma dose, the personal neutron dose and the intra-personal radiation dose.
2. The nuclear risk assessment method according to claim 1, wherein the step B21 includes:
step B211, estimating gamma dose of staff in different working areas according to activity of the point-like source in the working area, distance between the working area and the point-like source and residence time of the working area, wherein an estimation formula of the gamma dose of the staff in the different working areas is as follows:
；
wherein X is j Gamma dose for the j-th working area, the unit is Gy, j is an integer greater than 0; q (Q) j The unit is Bq for the point source activity of the j-th working area; Γ is a constant 3.42×10 -13 The unit is Gy.m 2 /(h·Bq)；T j The residence time of the jth working area is given in h; r is R j The unit is m, which is the distance between the jth working area and the point source;
step B212, estimating personal gamma dose of staff according to gamma dose of staff in different working areas, wherein an estimation formula of the personal gamma dose is as follows:
；
Wherein X is Total (S) Personal gamma dose for staff, in Gy; x is X j The gamma dose for the j-th working region, j being an integer greater than 0.
3. The method for risk assessment according to claim 1, wherein the step B22 includes:
step B221, measured from the overhead of the work area 24 The initial counting rate of Na gamma is used for estimating neutron dose of staff in different working areas, and an estimation formula of the neutron dose of the staff in the different working areas is as follows:
；
wherein,,neutron dose of staff in a j-th working area is given in Gy, and j is an integer larger than 0; f (f) j Is the coefficient related to the irradiation and measurement time in the jth working area, and is expressed as s -1 ；D Fj The unit of the absorption dose generated for the unit neutron fluence of the jth working area is Gy cm 2 Neutrons; n (t) 0 ) j Measured at the top of the head for the jth working area 24 Na gamma initial count rate in neutron s/cm 2 ；
Step B222, estimating personal neutron dose of staff according to neutron dose of staff in different working areas, wherein an estimation formula of the personal neutron dose is as follows:
；
wherein,,personal neutron dose for staff, in Gy; />Neutron dose of staff in the j-th working area is given in Gy, and j is an integer greater than 0.
4. The method for risk assessment according to claim 1, wherein the step B23 includes:
step B231, estimating the effective dose of the corresponding nuclide to be accumulated in the corresponding working area according to the residence time of the working area and the air activity concentration of the nuclide, wherein the estimation mode of the effective dose of the corresponding nuclide to be accumulated in the corresponding working area is as follows:
；
wherein E (i) j For nuclide i in the jth region of operationThe unit of the effective dose to be accumulated is mSv, and j is an integer greater than 0; c (C) ij The air activity concentration of the nuclide i in the jth working area is expressed as Bq/m 3 The method comprises the steps of carrying out a first treatment on the surface of the B is the respiration rate of the person, and the unit is m 3 /h；T j The stay time of the staff in the j-th working area is h; e, e i The unit is mSv/Bq, which is the dose conversion coefficient of the nuclide i;
step B232, estimating the sum of the effective doses of the corresponding nuclides to be integrated in different working areas according to the effective doses of the corresponding nuclides to be integrated in the corresponding working areas, wherein the estimation formula of the sum of the effective doses of the corresponding nuclides to be integrated in different working areas is as follows:
；
wherein E is i The unit is mSv, which is the sum of the effective doses to be integrated of the nuclide i in different working areas; e (i) j For the effective dose to be accumulated of the nuclide i in the j-th working area, the unit is mSv, and j is an integer greater than 0;
Step B233, estimating the irradiation dose in the individual according to the sum of the effective doses to be integrated of the corresponding nuclides in different working areas, wherein the estimation formula of the irradiation dose in the individual is as follows:
；
wherein E is Total (S) The dose of irradiation in the personnel of the staff is given in mSv; e (E) i The sum of the resulting to-be-integrated effective doses of the nuclide i in different working regions is given in mSv.
5. The nuclear risk assessment method according to claim 1, wherein in the step B4, the post radiation dose includes an in-post irradiation dose, a post gamma dose, and a post neutron dose, wherein the post irradiation dose is a sum of personal irradiation doses of different employees corresponding to the post, the post gamma dose is a sum of personal gamma doses of different employees corresponding to the post, and the post neutron dose is a sum of personal neutron doses of different employees corresponding to the post.
6. The nuclear risk assessment method according to claim 5, wherein in the step B5, the task radiation dose includes an intra-task radiation dose, a task γ dose, and a task neutron dose, wherein the intra-task radiation dose is a sum of intra-post radiation doses corresponding to different posts of the task, the task γ dose is a sum of post γ doses corresponding to different posts of the task, and the task neutron dose is a sum of post neutron doses corresponding to different posts of the task.
7. The nuclear risk assessment method according to any one of claims 1 to 6, wherein the step B6 includes:
performing risk assessment on the personal radiation dose according to the personal preset radiation dose to obtain a first risk assessment result;
performing risk assessment on the post radiation dose according to the post preset radiation dose to obtain a second risk assessment result;
performing risk assessment on the task radiation dose according to the task preset radiation dose to obtain a third risk assessment result;
and obtaining the nuclear-involved risk assessment result according to the first risk assessment result, the second risk assessment result and the third risk assessment result.
8. A nuclear risk assessment system for implementing a nuclear risk assessment method according to any one of claims 1-7, the nuclear risk assessment system comprising:
the acquisition module is used for acquiring detection data;
the personal radiation estimation module is used for estimating the personal radiation dose of staff according to the detection data;
the personal dose information recording module is used for updating the personal dose information file of the staff according to the personal radiation dose of the staff;
The post radiation estimation module is used for estimating post radiation doses corresponding to the posts according to the personal radiation doses of different staff at the same post;
the task radiation estimation module is used for estimating task radiation doses of corresponding tasks according to the post radiation doses of different posts of the same task; and
and the nuclear risk assessment module is used for carrying out nuclear risk assessment according to the personal radiation dose, the post radiation dose and the task radiation dose to obtain a nuclear risk assessment result.
9. A computer readable medium, on which a computer program is stored, characterized in that the program, when being processed and executed, implements the nuclear risk assessment method according to any one of claims 1-7.
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