CN111159834B - Complex environment emission/release nuclide dosage calculation method - Google Patents
Complex environment emission/release nuclide dosage calculation method Download PDFInfo
- Publication number
- CN111159834B CN111159834B CN201811312859.0A CN201811312859A CN111159834B CN 111159834 B CN111159834 B CN 111159834B CN 201811312859 A CN201811312859 A CN 201811312859A CN 111159834 B CN111159834 B CN 111159834B
- Authority
- CN
- China
- Prior art keywords
- calculating
- nuclide
- dose
- nuclear facility
- height
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
Images
Landscapes
- Measurement Of Radiation (AREA)
Abstract
The invention discloses a method for calculating the dosage of a complex environment emission/release nuclide, which comprises the following steps: calculating nuclide concentrations at different distances in downwind direction according to nuclear facility release source items; calculating the concentration of wind direction nuclides under the smoke plume center line of the complex environment according to the topographic features of the nuclear facility plant site; calculating the emission height of the smoke plume of the complex environment of the nuclear facility when the atmospheric stability is neutral or unstable; calculating the radionuclide concentration of the nuclear facility released smoke plume center line downwind under the influence of the surface roughness; calculating accident atmospheric dispersion factors of the complex environment of the nuclear facility in different time periods; and calculating public personal effective dose and thyroid gland dose caused by radionuclides when the nuclear facility complex environment accident is released. The advantages are that: the calculation method is scientific and reasonable, has strong applicability, is an important technical means for evaluating the radionuclide environmental impact under complex environmental conditions, and has important significance in the technical field of radionuclide atmospheric environmental impact evaluation.
Description
Technical Field
The invention belongs to a radionuclide environmental impact evaluation method of nuclear facilities under complex environmental conditions, and particularly relates to a radionuclide emission/release dosage calculation method of complex environments.
Background
When the nuclear facility happens, the radionuclide can be released into the atmosphere in the forms of gas, aerosol and the like, and the radionuclide causes radiation influence on the public through the atmosphere diffusion process and different irradiation ways. The nuclear facility environmental impact evaluation method provides a nuclear facility radionuclide atmospheric diffusion and dose impact calculation method.
However, the existing nuclear facility radionuclide atmospheric diffusion and dose calculation method has the following problems, on one hand, the calculation requires the flat site topography; and secondly, the influence of the actual surface roughness of the plant site of the nuclear facility is not considered. The prior radionuclide atmospheric diffusion and dose calculation method does not consider the influence of complex terrain conditions and surface roughness on radionuclide atmospheric environment influence evaluation. The difference of the plant site of the nuclear facility due to the geographical position and the surface environmental characteristics is remarkable, the radionuclide emission characteristics are greatly different, the radionuclide concentration distribution characteristics released by accidents and the doses caused by the radionuclides under the complex environmental conditions of the nuclear facility are the important concerns for evaluating the environmental effects of the nuclear facility, and a good method for calculating the doses caused by the nuclides released by the complex environment of the nuclear facility does not exist in the prior art.
Disclosure of Invention
The invention aims to provide a method for calculating the dosage of the nuclide released by a complex environment, which can well calculate the dosage caused by the nuclide released by the complex environment of a nuclear facility.
The technical scheme of the invention is as follows: a complex environment emission/release nuclide dose calculation method comprises the following steps:
(1) Analyzing the atmospheric diffusion characteristics of the radionuclides under the complex environment of the nuclear facility based on meteorological observation data, and calculating the nuclide concentrations CON (x, y, z) at different distances in the downwind direction according to the release source item of the nuclear facility;
(2) Calculating the wind direction nuclide concentration CON (x, 0, z) under the smoke plume central line of the complex environment according to the topographic features of the nuclear facility plant site;
(3) Calculating the emission height of the smoke plume of the complex environment of the nuclear facility when the atmospheric stability is neutral or unstable;
(4) Calculating the radionuclide concentration of the nuclear facility released smoke plume center line downwind under the influence of the surface roughness;
(5) Calculating accident atmospheric dispersion factors of different time periods of the complex environment of the nuclear facility by using an interpolation method;
(6) And calculating public personal effective dose and thyroid gland dose caused by radionuclides when the nuclear facility complex environment accident is released.
The mode for calculating the nuclide concentrations at different distances in the downwind direction in the step (1) is as follows:
wherein CON (x, y, z) is the concentration of the species at the downwind distance (x, y, z), S H Is of strong origin (Bq/s), w s Is the average wind speed, sigma y Is the standard deviation of the concentration distribution function in the y direction, sigma z Is the standard deviation of the concentration distribution function in the z direction, M is the height of the covering temperature inversion layer, H g0 Is the terrain height, z is the vertical height, and h is the plume centerline height.
The mode for calculating the down wind nuclide concentration of the smoke plume center line in the step (2) is as follows:
wherein CON (x, 0, z) is the concentration of the nuclide in the downwind direction of the plume center line, S H Is of strong origin (Bq/s), w s Is the average wind speed, sigma y Is the standard deviation of the concentration distribution function in the y direction, sigma z Is the standard deviation of the z-direction concentration distribution function, h is the plume centerline height, and M is the cover anti-temperature layer height.
The method for calculating the emission height of the smoke plume in the step (3) is as follows:
HCOR is plume emission height, Δh is plume lifting height.
Wherein, the liquid crystal display device comprises a liquid crystal display device,
(when the atmosphere is stable)In neutral or unstable conditions), Δh is plume lifting height, S is sensible heat flux, d x Is downwind distance->
Is the wind speed at the z-height, wherein,
is the wind speed at the reference altitude, r 0 Is the surface roughness and p is an exponential parameter.
The method for calculating the radionuclide concentration in the downwind direction of the released smoke plume center line under the influence of the surface roughness in the step (4) is as follows:
CONCOR (x, 0, z) is the corrected plume centerline downwind nuclide concentration,
wherein, the liquid crystal display device comprises a liquid crystal display device,
σ z，cor to correct the standard deviation of the z-direction concentration distribution function, consider the influence of the surface roughness, sigma z，pg Is the vertical diffusion parameter of the P-G curve, r cor For adjusting the surface roughness, r pg Is the surface roughness of the P-G curve.
The method for calculating the atmospheric diffusion factors of accidents in different time periods of the complex environment in the step (5) is as follows:
ADF i is the atmospheric dispersion factor value (s/m 3 )
Wherein, the liquid crystal display device comprises a liquid crystal display device,
ADF T1 an atmospheric dispersion factor of 0 to T1, ADF T2 An atmospheric dispersion factor of 0 to T2, ADF T2-T1 Is the atmospheric diffusion factor at the moment T2-T1.
The method for calculating the public personal effective dose caused by the radionuclide in the step (6) when the complex environmental accident is released is as follows:
Dose＝Dose imm +Dose inh
Dose imm to submerge the external irradiation Dose, dose inh For inhalation of internal radiation dose
The method for calculating the immersion external irradiation dose comprises the following steps:
the calculation mode of the irradiation dose in inhalation is as follows:
br is the respiration rate of an adult,
inhalation of an effective dose-converting factor to a public individual of nuclide j.
The method for calculating the dosage of the public thyroid gland caused by the radionuclide in the step (6) when the complex environmental accident is released is as follows:
The invention has the beneficial effects that: the calculation method is based on meteorological observation data, and the atmospheric diffusion characteristics of the radionuclide and the public radiation dose caused under the complex environmental conditions are calculated by combining source items. The calculation method is scientific and reasonable, has strong applicability, is an important technical means for evaluating the radionuclide environmental impact under complex environmental conditions, and has important significance in the technical field of radionuclide atmospheric environmental impact evaluation.
Drawings
FIG. 1 is a flow chart of a method for calculating the dosage of a complex environmental emission/release nuclide provided by the present invention.
Detailed Description
The invention will be described in further detail with reference to the accompanying drawings and specific examples.
A complex environment emission/release nuclide dose calculation method comprises the following steps:
(1) Analyzing the atmospheric diffusion characteristics of the radionuclides under the complex environment of the nuclear facility based on meteorological observation data, and calculating the nuclide concentrations CON (x, y, z) at different distances in the downwind direction according to the release source item of the nuclear facility;
the mode of calculating the nuclide concentration at different distances down wind direction is:
wherein CON (x, y, z) is the concentration of the species at the downwind distance (x, y, z), S H Is of strong origin (Bq/s), w s Is the average wind speed, sigma y Is the standard deviation of the concentration distribution function in the y direction, sigma z Is the standard deviation of the concentration distribution function in the z direction, M is the height of the covering temperature inversion layerDegree of H g0 Is the terrain height, z is the vertical height, and h is the plume centerline height.
(2) Calculating the wind direction nuclide concentration CON (x, 0, z) under the smoke plume central line of the complex environment according to the topographic features of the nuclear facility plant site;
the mode for calculating the nuclide concentration of the downwind direction of the smoke plume center line is as follows:
wherein CON (x, 0, z) is the concentration of the nuclide in the downwind direction of the plume center line, S H Is of strong origin (Bq/s), w s Is the average wind speed, sigma y Is the standard deviation of the concentration distribution function in the y direction, sigma z Is the standard deviation of the z-direction concentration distribution function, h is the plume centerline height, and M is the cover anti-temperature layer height.
(3) Calculating the emission height of the smoke plume of the complex environment of the nuclear facility when the atmospheric stability is neutral or unstable;
the mode of calculating the emission height of the smoke plume is as follows:
HCOR is plume emission height, Δh is plume lifting height.
Wherein, the liquid crystal display device comprises a liquid crystal display device,
(when the atmospheric stability is neutral or unstable)
Δh is plume lifting height, S is sensible heat flux, d x Is the distance in the downwind direction and the distance in the downwind direction,
is the wind speed at z-height.
Wherein, the liquid crystal display device comprises a liquid crystal display device,
(4) Calculating the radionuclide concentration of the nuclear facility released smoke plume center line downwind under the influence of the surface roughness;
the method for calculating the radionuclide concentration of the released plume center line downwind under the influence of the surface roughness is as follows:
CONCOR (x, 0, z) is the corrected plume centerline downwind nuclide concentration.
Wherein, the liquid crystal display device comprises a liquid crystal display device,
σ z，cor the effect of surface roughness is taken into account for the standard deviation of the corrected z-direction concentration profile function. Sigma (sigma) z，pg Is the vertical diffusion parameter of the P-G curve, r cor For adjusting the surface roughness, r pg Is the surface roughness of the P-G curve.
(5) Calculating accident atmospheric dispersion factors of different time periods of the complex environment of the nuclear facility by using an interpolation method;
the method for calculating the atmospheric diffusion factors of the accidents in different time periods of the complex environment is as follows:
ADF i is the atmospheric dispersion factor value (s/m 3) at different moments
Wherein, the liquid crystal display device comprises a liquid crystal display device,
ADF T1 an atmospheric dispersion factor of 0 to T1, ADF T2 An atmospheric dispersion factor of 0 to T2, ADF T2-T1 Is the atmospheric diffusion factor at the moment T2-T1.
(6) And calculating public personal effective dose and thyroid gland dose caused by radionuclides when the nuclear facility complex environment accident is released.
The method for calculating the public personal effective dose caused by the radionuclide when complex environmental accidents are released is as follows:
Dose＝Dose imm +Dose inh
Dose imm to submerge the external irradiation Dose, dose inh For inhalation of internal radiation dose
The method for calculating the immersion external irradiation dose comprises the following steps:
The calculation mode of the irradiation dose in inhalation is as follows:
br is the respiration rate of an adult,
inhalation of an effective dose-converting factor to a public individual of nuclide j.
The method for calculating the public thyroid doses caused by radionuclides during the release of complex environmental accidents is as follows:
FIG. 1 shows a flow chart of a method for calculating the dosage of a complex environmental emission/release nuclide in an embodiment of the present invention, which mainly comprises the following steps:
(1) Analyzing the atmospheric diffusion characteristics of the radionuclides under the complex environment based on meteorological observation data, and calculating the nuclide concentrations CON (x, y, z) at different distances in the downwind direction;
in the embodiment, firstly, the plant site dominant wind direction is analyzed based on meteorological observation data, the standard deviation of concentration distribution functions in the y direction and the z direction is calculated according to plant site conditions, the nuclide concentrations at different distances in the downwind direction are calculated by combining plant accident source item data, and the influence of complex topography on the nuclide concentrations is considered.
(2) Calculating the wind direction nuclide concentration CON (x, 0, z) under the smoke plume central line of the complex environment according to the topographic features of the nuclear facility plant site;
in the step, the down-wind nuclide concentration of the smoke plume center line in the complex environment is calculated, the diffusion of the smoke plume in the y direction is not considered in the embodiment, the down-wind nuclide concentration of the smoke plume center line is mainly determined through a calculation formula, and the influence of the smoke plume lifting effect and the surface roughness is not considered in emission calculation.
(3) Calculating the emission height of the smoke plume of the complex environment of the nuclear facility when the atmospheric stability is neutral or unstable;
in the embodiment, the wind speed at the z height is calculated first, the lifting height of the smoke plume is calculated by using the wind speed data at the z height, and the smoke plume emission height is determined by combining the discharge outlet height and the smoke plume lifting height.
(4) Calculating the radionuclide concentration of the nuclear facility released smoke plume center line downwind under the influence of the surface roughness;
in this embodiment, the actual surface roughness of the plant site of the nuclear facility is determined according to the surface characteristics of the plant site of the nuclear facility, and compared with the surface roughness in the P-G curve, and the standard deviation of the actual z-direction concentration distribution function of the plant site of the nuclear facility is determined by using the ratio of the actual surface roughness to the surface roughness of the P-G curve. And (3) calculating the radionuclide concentration in the downwind direction of the center line of the smoke of the nuclear facility released under the influence of the surface roughness of the plant site of the nuclear facility according to the actual discharge height of the smoke of the complex environment of the nuclear facility and the standard deviation of the actual concentration distribution function in the z direction, and comparing with the radionuclide concentration CON (x, 0, z) in the step (2) in the downwind direction of the center line of the smoke of the complex environment according to the topographic features of the plant site of the nuclear facility, so as to determine the influence degree of the surface roughness.
(5) Calculating accident atmospheric dispersion factors of different time periods of the complex environment of the nuclear facility by using an interpolation method;
according to the method, the atmospheric dispersion factors of accidents in different time periods of the complex environment of the nuclear facility are calculated by using an interpolation method, and the atmospheric dispersion factors in different time periods of the complex environment of the nuclear facility plant site are calculated by using the ratio of the radionuclide concentration in the wind direction below the center line of the smoke plume released by the nuclear facility under the influence of the surface roughness of the plant site of the nuclear facility. According to the radionuclide release characteristics of different time periods, the atmospheric diffusion factors of different time periods such as 0-2h,2-8h,8-24h,24-96h and 96-720h are obtained by interpolation calculation through an interpolation method.
(6) And calculating public personal effective dose and thyroid gland dose caused by radionuclides when the nuclear facility complex environment accident is released.
In the embodiment, the public personal effective dose and thyroid dose caused by the radionuclide are obtained by summing the immersion external irradiation dose and the inhalation internal irradiation dose, and the immersion external irradiation dose and the inhalation internal irradiation dose are obtained by a dose calculation formula under the corresponding complex environmental conditions of the nuclear facility. Thyroid dosages were obtained by thyroid dosage calculation formula.
The calculation method is scientific and reasonable, is an important technical means for radionuclide atmospheric environmental impact analysis under the complex environmental conditions of nuclear facilities, has important significance in the field of radionuclide atmospheric environmental impact evaluation and radiation environmental impact analysis when the environment of nuclear facility factories is complex, and can be widely applied to radionuclide atmospheric environmental impact evaluation of nuclear facilities.
It will be apparent to those skilled in the art that various modifications and variations can be made to the present invention without departing from the spirit or scope of the invention. Any modifications and variations which come within the spirit and principles of the invention are desired to be covered by the appended claims and their equivalents.
Claims (1)
1. A method for calculating the emission/release nuclide dosage of a complex environment is characterized by comprising the following steps: the method comprises the following steps:
(1) Analyzing the atmospheric diffusion characteristics of the radionuclides under the complex environment of the nuclear facility based on meteorological observation data, and calculating the nuclide concentrations CON (x, y, z) at different distances in the downwind direction according to the release source item of the nuclear facility;
(2) Calculating the wind direction nuclide concentration CON (x, 0, z) under the smoke plume central line of the complex environment according to the topographic features of the nuclear facility plant site;
(3) Calculating the emission height of the smoke plume of the complex environment of the nuclear facility when the atmospheric stability is neutral or unstable;
(4) Calculating the radionuclide concentration of the nuclear facility released smoke plume center line downwind under the influence of the surface roughness;
(5) Calculating accident atmospheric dispersion factors of different time periods of the complex environment of the nuclear facility by using an interpolation method;
(6) Calculating public personal effective dose and thyroid gland dose caused by radionuclides when the nuclear facility complex environment accident is released;
the mode for calculating the nuclide concentrations at different distances in the downwind direction in the step (1) is as follows:
wherein CON (x, y, z) is the concentration of the species at the downwind distance (x, y, z), S H Is the source strength Bq/s, w s Is the average wind speed, sigma y Is the standard deviation of the concentration distribution function in the y direction, sigma z Is the standard deviation of the concentration distribution function in the z direction, M is the height of the covering temperature inversion layer, H g0 Is the terrain height, z is the vertical height, and h is the plume center line height;
the mode for calculating the down wind nuclide concentration of the smoke plume center line in the step (2) is as follows:
wherein CON (x, 0, z) is the concentration of the nuclide in the downwind direction of the plume center line, S H Is the source strength Bq/s, w s Is the average wind speed, sigma y Is the standard deviation of the concentration distribution function in the y direction, sigma z The standard deviation of the concentration distribution function in the z direction is that h is the height of the center line of the smoke plume, and M is the height of the covering temperature inversion layer;
the method for calculating the emission height of the smoke plume in the step (3) is as follows:
HCOR is the plume emission height, Δh is the plume lifting height;
wherein, the liquid crystal display device comprises a liquid crystal display device,
when the atmospheric stability is neutral or unstable, Δh is plume rise height, S is sensible heat flux, d x Is downwind distance->
Is the wind speed at z-height, wherein +.>
Is the wind speed at the reference altitude, r 0 Is the surface roughness, p is an exponential parameter;
the method for calculating the radionuclide concentration in the downwind direction of the released smoke plume center line under the influence of the surface roughness in the step (4) is as follows:
CONCOR (x, 0, z) is the corrected plume centerline downwind nuclide concentration,
wherein, the liquid crystal display device comprises a liquid crystal display device,
σ z，cor to correct the standard deviation of the z-direction concentration distribution function, consider the influence of the surface roughness, sigma z，pg Is the vertical diffusion parameter of the P-G curve, r cor For adjusting the surface roughness, r pg Surface roughness for the P-G curve;
the method for calculating the atmospheric diffusion factors of accidents in different time periods of the complex environment in the step (5) is as follows:
ADF i is the atmospheric diffusion factor value s/m at different moments 3
Wherein, the liquid crystal display device comprises a liquid crystal display device,
ADF T1 an atmospheric dispersion factor of 0 to T1, ADF T2 Atmospheric dispersion factor, AD, from 0 to T2F T2-T1 Is the atmospheric diffusion factor at the moment of T2-T1;
the method for calculating the public personal effective dose caused by the radionuclide in the step (6) when the complex environmental accident is released is as follows:
Dose＝Dose imm +Dose inh
Dose imm to submerge the external irradiation Dose, dose inh For inhalation of internal radiation dose
The method for calculating the immersion external irradiation dose comprises the following steps:
the calculation mode of the irradiation dose in inhalation is as follows:
br is the respiration rate of an adult,
inhalation of an effective dose-converting factor for a public individual of nuclide j;
the method for calculating the dosage of the public thyroid gland caused by the radionuclide in the step (6) when the complex environmental accident is released is as follows:
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811312859.0A CN111159834B (en) | 2018-11-06 | 2018-11-06 | Complex environment emission/release nuclide dosage calculation method |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811312859.0A CN111159834B (en) | 2018-11-06 | 2018-11-06 | Complex environment emission/release nuclide dosage calculation method |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN111159834A CN111159834A (en) | 2020-05-15 |
| CN111159834B true CN111159834B (en) | 2023-07-14 |
Family
ID=70554351
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201811312859.0A Active CN111159834B (en) | 2018-11-06 | 2018-11-06 | Complex environment emission/release nuclide dosage calculation method |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN111159834B (en) |
Families Citing this family (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111999754B (en) * | 2020-07-10 | 2022-11-25 | 中国辐射防护研究院 | Evaluation system based on nuclear facility airborne effluent monitoring data |
| CN112683719B (en) * | 2020-11-25 | 2023-07-25 | 中国辐射防护研究院 | Nuclear material ignition accident condition release source item measuring device and evaluation method |
| CN112990643B (en) * | 2020-12-15 | 2022-03-22 | 中国辐射防护研究院 | Design method of dosage calculation system under accident condition |
| CN114220564A (en) * | 2021-11-02 | 2022-03-22 | 中国核电工程有限公司 | Containment pressure relief strategy determination method based on radioactive release |
| CN115586562B (en) * | 2022-10-14 | 2023-04-28 | 核工业航测遥感中心 | Method for monitoring aviation of radioactive smoke plume |
Citations (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2005003644A (en) * | 2003-06-16 | 2005-01-06 | Mitsubishi Heavy Ind Ltd | Contaminant diffusion prediction system and security system |
| CN104424388A (en) * | 2013-08-29 | 2015-03-18 | 中核第四研究设计工程有限公司 | Method for comprehensive evaluation of uranium mining and milling atmospheric radiation environment |
| CN104933294A (en) * | 2015-05-25 | 2015-09-23 | 苏州热工研究院有限公司 | Method for constructing migration and propagation evaluation model of radioactive substance |
| CN106469245A (en) * | 2015-08-14 | 2017-03-01 | 中国辐射防护研究院 | The Annul radiation dose computational methods of nuclear power plant's liquid radioactive substance and system |
| CN106528926A (en) * | 2016-09-29 | 2017-03-22 | 长江勘测规划设计研究有限责任公司 | Underground nuclear power station smoke plume contingency planning zone division method |
| CN107330187A (en) * | 2017-06-30 | 2017-11-07 | 哈尔滨工程大学 | A kind of elimination of nuclear facilities radiation field dosage distributed simulation method |
| CN107526908A (en) * | 2016-06-21 | 2017-12-29 | 中国辐射防护研究院 | Lagrangian cigarette group Air Dispersion Modeling method in the evaluation of nuclear accident Off-Site consequence |
| CN107526852A (en) * | 2016-06-21 | 2017-12-29 | 中国辐射防护研究院 | A kind of nuclear facilities Accident Off-site Consequence real-time online evaluation method and system |
| CN107526095A (en) * | 2016-06-21 | 2017-12-29 | 中国辐射防护研究院 | Airborne approach food chain radioactive activity evaluation method in nuclear accident Consequence Assessment |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US10296670B2 (en) * | 2014-09-17 | 2019-05-21 | Infineon Technologies Ag | Age estimator for safety monitoring based on local detectors |
-
2018
- 2018-11-06 CN CN201811312859.0A patent/CN111159834B/en active Active
Patent Citations (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2005003644A (en) * | 2003-06-16 | 2005-01-06 | Mitsubishi Heavy Ind Ltd | Contaminant diffusion prediction system and security system |
| CN104424388A (en) * | 2013-08-29 | 2015-03-18 | 中核第四研究设计工程有限公司 | Method for comprehensive evaluation of uranium mining and milling atmospheric radiation environment |
| CN104933294A (en) * | 2015-05-25 | 2015-09-23 | 苏州热工研究院有限公司 | Method for constructing migration and propagation evaluation model of radioactive substance |
| CN106469245A (en) * | 2015-08-14 | 2017-03-01 | 中国辐射防护研究院 | The Annul radiation dose computational methods of nuclear power plant's liquid radioactive substance and system |
| CN107526908A (en) * | 2016-06-21 | 2017-12-29 | 中国辐射防护研究院 | Lagrangian cigarette group Air Dispersion Modeling method in the evaluation of nuclear accident Off-Site consequence |
| CN107526852A (en) * | 2016-06-21 | 2017-12-29 | 中国辐射防护研究院 | A kind of nuclear facilities Accident Off-site Consequence real-time online evaluation method and system |
| CN107526095A (en) * | 2016-06-21 | 2017-12-29 | 中国辐射防护研究院 | Airborne approach food chain radioactive activity evaluation method in nuclear accident Consequence Assessment |
| CN106528926A (en) * | 2016-09-29 | 2017-03-22 | 长江勘测规划设计研究有限责任公司 | Underground nuclear power station smoke plume contingency planning zone division method |
| CN107330187A (en) * | 2017-06-30 | 2017-11-07 | 哈尔滨工程大学 | A kind of elimination of nuclear facilities radiation field dosage distributed simulation method |
Non-Patent Citations (6)
| Title |
|---|
| Raza，SS et al..A comparison of direct gamma dose rates from a stationary Gaussian plume using different models.《Nuclear Technology》.2002,全文. * |
| S.Van Thielen et al..Optimizing the calculation grid for atmospheric dispersion modelling.《Journal of Environmental Radioactivity》.2015,全文. * |
| Zhang Q et al..radioactive airborne effluents and the environmental impact assessment of CAP1400 nuclear power plant under normal operation.《Nuclear Engineering and Design》.2014,全文. * |
| 刘爽.核设施事故排放气载放射性污染物扩散模拟研究.《中国优秀硕士学位论文全文库 工程科技Ⅰ辑 》.2018,全文. * |
| 胡二邦 等.滨海复杂地形核电厂址高斯烟羽模式有效性检验.《辐射防护》.2004,全文. * |
| 郭瑞萍 等.基于拉格朗日方法的核电厂核素大气扩散特征研究.《2017中国环境科学学会科学与技术年会论文集（第四卷）》.2017,全文. * |
Also Published As
| Publication number | Publication date |
|---|---|
| CN111159834A (en) | 2020-05-15 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN111159834B (en) | Complex environment emission/release nuclide dosage calculation method | |
| CN107145698A (en) | Core and radiation accident consequence large scale analogy method and simulation system | |
| Vasyanovich et al. | Determination of radionuclide composition of the Russian NPPs atmospheric releases and dose assessment to population | |
| Pirouzmand et al. | Dose assessment of radionuclides dispersion from Bushehr nuclear power plant stack under normal operation and accident conditions | |
| CN109559015A (en) | A kind of public dose evaluation method in Radiation Environmental Assessment based on probability theory | |
| Anvari et al. | Assessment of the total effective dose equivalent for accidental release from the Tehran Research Reactor | |
| CN107145700A (en) | Core and radiation accident consequence airborne radioactivity dosages of substance evaluation method | |
| Muswema et al. | Atmospheric dispersion modeling and radiological safety analysis for a hypothetical accident of Ghana Research Reactor-1 (GHARR-1) | |
| CN113539534B (en) | Method for measuring and calculating emergency plan area of spent fuel post-treatment plant | |
| Park et al. | Emergency preparedness for the accidental release of radionuclides from the Uljin Nuclear Power Plant in Korea | |
| Hatano et al. | Aerosol migration near Chernobyl: Long-term data and modeling | |
| CN112634114A (en) | Radiation environment management and evaluation method and system | |
| Castro et al. | Differences into HT and HTO concentrations in air into the Western Mediterranean Basin and Continental Europe and safety related issues | |
| Miller et al. | Estimates of dose to the population within fifty miles due to noble gas releases from the Three Mile Island incident | |
| Mavall | Modelling the dispersion of radionuclides in the atmosphere | |
| Wang et al. | Comparison of atmospheric radionuclide dispersion models for a risk-informed consequence-driven advanced reactor licensing framework | |
| Geraskin et al. | RC Code for Calculating Doses from Radioactive Releases to the Atmosphere | |
| Mourad | Source term and radiological consequences of the Chernobyl accident | |
| Pasciak et al. | A Method for Calculating Doses to the Population from 133Xe Releases During the Three Mile Island Accident | |
| Madear et al. | Radon dispersion air modeling in Banat mining area | |
| Fields et al. | Validation of the AIRDOS-EPA computer code by simulating intermediate range transport of 85Kr from the Savannah River Plant | |
| Policastro et al. | User's manual: cooling-tower-plume prediction code | |
| Overcamp | Modeling gamma absorbed dose due to meandering plumes | |
| Trimor | NESHAP Area-Specific Dose-Release Factors for Potential Onsite Member-of-the-Public Locations at SRS using CAP88-PC Version 4.0 | |
| Aliyu et al. | ENVIRONMENTAL IMPACT ASSESSMENT (EIA) IN NUCLEAR POWER PLANT SITING: USING STOCHASTIC ATMOSPHERIC DISPERSION MODELING TECHNIQUES |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |