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HJ 1155-2020: (Technical specifications for emergency monitoring of radiation accidents)
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(Technical specifications for emergency monitoring of radiation accidents)
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HJ 1155-2020
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Standard similar to HJ 1155-2020 HJ 1347.1 HJ 1347.2 HJ 1346.1 Basic data | Standard ID | HJ 1155-2020 (HJ1155-2020) | | Description (Translated English) | (Technical specifications for emergency monitoring of radiation accidents) | | Sector / Industry | Environmental Protection Industry Standard | | Word Count Estimation | 18,139 | | Date of Issue | 2020-12-30 | | Date of Implementation | 2021-03-01 | | Regulation (derived from) | Ministry of Ecology and Environment Announcement No. 76 [2020] | | Issuing agency(ies) | Ministry of Ecology and Environment | HJ 1155-2020: (Technical specifications for emergency monitoring of radiation accidents)---This is a DRAFT version for illustration, not a final translation. Full copy of true-PDF in English version (including equations, symbols, images, flow-chart, tables, and figures etc.) will be manually/carefully translated upon your order.
(Technical specifications for emergency monitoring of radiation accidents)
Technical specifications for emergency monitoring of radiation accidents
National Environmental Protection Standards of the People's Republic of China
2020-12-30 release
2021-3-1 implementation
Issued by the Ministry of Ecology and Environment
Table of contents
Foreword...III
1 Scope of application...1
2 Normative references...1
3 Terms and definitions...1
4 Purpose...2
5 General principles and overall requirements...3
6 On-site monitoring...3
7 Sampling and analysis...6
8 Safety protection of emergency personnel...7
9 Quality Assurance...8
10 Data Processing and Monitoring Report...8
Appendix A (informative appendix) the recommended range of the inner warning zone in the case of an emergency radiation accident caused by radioactive sources...10
Appendix B (informative appendix) Method for estimating the distance of gamma source based on the results of gamma radiation level monitoring...12
Appendix C (informative appendix) Method for estimating gamma source activity based on gamma radiation air absorbed dose rate...13
Appendix D (Informative Appendix) Personal Surface Monitoring Methods...14
Appendix E (informative appendix) Guidelines for controlling the exposure dose of emergency personnel...15
Foreword
To implement the Environmental Protection Law of the People’s Republic of China, the Law of the People’s Republic of China on the Prevention and Control of Radioactive Pollution, and the Nuclear
Safety Law, which regulates emergency monitoring of radiation accidents, has formulated this standard.
This standard specifies the general principles, content, methods and technical requirements for emergency monitoring of radiation accidents.
This standard is issued for the first time.
The appendix of this standard is an informative appendix.
This standard was formulated by the Department of Nuclear Facilities Safety Supervision and the Department of Regulations and Standards of the Ministry of Ecology and Environment.
Drafting organizations of this standard. Zhejiang Provincial Radiation Environment Monitoring Station (Radiation Environment Monitoring Technology Center of the Ministry of Ecology and Environment), the Ministry of Ecology and Environment
Radiation Safety Center, Guangdong Environmental Radiation Monitoring Center, Guangxi Zhuang Autonomous Region Radiation Environmental Supervision and Management Station.
This standard was approved by the Ministry of Ecology and Environment on December 30, 2020.
This standard will be implemented on March 1, 2021.
This standard is interpreted by the Ministry of Ecology and Environment.
Technical specifications for emergency monitoring of radiation accidents
1 Scope of application
This standard specifies the general principles of radiation accident emergency monitoring, on-site monitoring, sampling analysis, safety protection, quality assurance, data processing
Technical requirements such as management and monitoring reports.
This standard applies to the use of nuclear technology, the transportation of radioactive materials, and radioactive waste treatment, storage and disposal facilities or activities.
Emergency monitoring of radiation accidents.
Involving environmental radioactive pollution incidents caused by the development and utilization of uranium (thorium) mines and associated radioactive minerals, domestic and foreign spacecraft crashed in my country
Environmental radioactive pollution incidents caused by accidents, as well as emergency monitoring of overseas nuclear and radiation accidents and incidents that may have a radiation impact on the environment of our country.
Test work can be carried out by reference.
2 Normative references
The content of this standard refers to the clauses in the following documents. For undated reference documents, the effective version is applicable to this standard.
GB 18871 Basic standard for ionizing radiation protection and radiation source safety
GB/T 8170 Numerical rounding rules and the expression and determination of limit values
GB/T 10264 Personal Thermoluminescence Dose Measurement System for Personal and Environmental Monitoring
GB/T 11743 Analytical Method of γ Energy Spectrum for Radionuclides in Soil
GB/T 14056.1 Determination of Surface Contamination Part 1.β-emitter (Eβmax >0.15MeV) and α-emitter
GB/T 14583 Specification for determination of environmental surface gamma radiation dose rate
HJ/T 61 Technical Specification for Radiation Environmental Monitoring
HJ 1127 Environmental sample gamma nuclide measurement technical specification in emergency monitoring
HJ 1129 Technical specification for measuring gamma nuclide in soil with in-situ high-purity germanium spectrometer
GBZ/T 216 Specification for the treatment of radionuclide contamination on the human body surface
3 Terms and definitions
The following terms and definitions apply to this standard.
3.1 Radiation accident
It mainly refers to the loss, theft, or loss of control of radioactive sources in the following facilities or activities, or the loss of control of radioactive materials and radiation devices that cause people to suffer
- 2 -
Unexpected abnormal exposure, or incidents that cause environmental radioactive pollution.
(1) Utilization of nuclear technology;
(2) Transport of radioactive materials;
(3) Treatment, storage and disposal of radioactive waste.
3.2 (radiation) source
All substances or entities that can cause radiation exposure by emitting ionizing radiation or releasing radioactive substances. For example, the gamma irradiation device is
The source in the practice of food preservation by irradiation, X-ray machines can be the source in the practice of radiological diagnosis.
3.3 Radioactive sources
It refers to materials that are permanently sealed in a container or have a tight cladding and are solid, except for materials in the nuclear fuel cycle of research reactors and power reactors.
Radioactive material.
3.4 radioactive contamination
Due to human activities, radioactive materials that exceed national standards or appear on the surface or inside of materials, human bodies, places, environmental media, or
Rays. The pollution mentioned in this standard refers to radioactive pollution.
3.5 Radiation accident emergency monitoring radiation accident emergency monitoring
In the case of a radiation accident, it is necessary to find out the nuclide, location, state and radioactive contamination of the site or the environment of the radioactive material.
Monitoring of radiation levels. Referred to as emergency monitoring in this standard.
3.6 emergency worker
Personnel directly or indirectly involved in the command, organization, sampling, monitoring, handling, support, and standby of radiation accident emergency monitoring.
3.7 comparison point
Refers to the specific assessment of the degree of environmental radioactive pollution in a radiation accident area, which is located outside the radiation accident area and can provide this area
The point of the environmental radiation background value.
3.8 precautionary area
In the event of an accident, in order to control the radiation dose or prevent the spread of pollution, it is necessary to take special protective measures or safety measures to control
The area where people and objects enter and exit. The guard zone is generally divided into an inner guard zone and an outer guard zone.
4 purpose
The main purpose of implementing emergency monitoring is to protect public health and the safety of the radiation environment, to reduce the harm caused by accidents, and to make judgments and assessments of accidents.
Provide data for emergency decision-making; provide monitoring data needed to determine the implementation of emergency protective actions;
Quantitative assessment provides key data; searches for lost, stolen, and out-of-control radioactive materials; and provides the public with monitoring data on the radiation environment.
5 General principles and general requirements
5.1 General principles
5.1.1 Quick response. Emergency monitoring should respond quickly and obtain monitoring results as soon as possible.
5.1.2 Prioritize priority. Priority should be given to the monitoring of the accident site and the surrounding areas of personnel activities that may be affected, and the warning zone should be determined as soon as possible.
5.1.3 Risk orientation. The scope of emergency monitoring, monitoring items, input power, etc. should be determined according to the size of the accident source item and the possible consequences
content.
5.1.4 The data is reliable. Effective quality assurance measures should be taken to ensure the accuracy and reliability of monitoring data.
5.2 General requirements
5.2.1 Through the inquiries of accident-related personnel (such as management, technical and user personnel, and patients with radiation sickness, etc.) and the adjustment of relevant information
The accident information was collected through various channels such as investigations, and the source type, status, nuclide type, radiation type, activity size, shielding situation,
Information such as quantity, source, production or use unit, and the accident site and surrounding environmental conditions.
5.2.2 Carry out emergency monitoring plan design based on source items and on-site environmental conditions. The emergency monitoring plan should quickly determine the source’s characteristics, location and
For the purpose of on-site environmental radiation level, the content should include accident overview, monitoring tasks or targets, monitoring scope, monitoring items, monitoring instruments and
Methods, sampling locations, safety protection and quality assurance, etc.
5.2.3 Emergency monitoring is based on X/γ radiation surrounding dose equivalent (rate), neutron radiation surrounding dose equivalent (rate), α/β surface pollution level and
Ground gamma nuclide energy spectrum analysis and other on-site monitoring are the main tasks, and sampling and analysis are carried out when necessary.
5.2.4 It should be ensured that the range of the monitoring instrument meets the requirements of emergency monitoring. Generally, the high range of the X/γ radiation level monitor should not be lower than
100mSv/h.
5.2.5 A monitoring instrument with a long pole and sound and light alarm function should be used to ensure that the monitoring personnel maintain a safe distance as far as possible from the potential source.
And get sound and light alarm information in time.
5.2.6 Ensure the effectiveness and reliability of the monitoring equipment during the emergency monitoring process, and at the same time have a certain amount of redundancy or backup.
5.2.7 Emergency personnel should do a good job of personal safety protection during the whole process of emergency monitoring.
6 On-site monitoring
6.1 Source search
6.1.1 Through the analysis and judgment of the accident information, the potential location and influence range of the source are estimated, and the search plan is determined.
6.1.2 Generally, the potential position of the source is the center, and the search is carried out from a multi-directional, gradually approaching measurement method from the outside and the inside.
6.1.3 The moving speed of the search should meet the response time requirements of the instrument, and the distance between the routes should meet the coverage of the monitored area. The instrument probe
Avoid contact with the surface of the object to be tested.
6.1.4 When searching for gamma/neutron sources in a large range, vehicle-mounted surveys, aerial surveys, remote control surveys, and comprehensive use of multiple surveys can be used.
6.1.5 During the search, pay close attention to the readings of the radiation monitor and the sound and light alarm information. Once an area with an abnormally elevated radiation level is detected, it should be
Increase the monitoring point and monitoring frequency for measurement confirmation.
6.1.6 Determine the warning zone based on accident information, on-site environmental conditions and search and measurement results (see Appendix A).
6.1.7 In the inner warning zone, the location of the source can be further determined by X/γ radiation level, neutron radiation level or surface contamination measurement. also may
Assist in determining the location of the source by methods such as metal detection, photography and camera identification.
6.1.8 In dangerous areas where the dose rate level exceeds 100mSv/h in the inner warning zone, the location of the source should be determined by the remote control measurement method.
6.1.9 For gamma sources, the distance to the source can be estimated based on the monitoring results of gamma radiation levels (see Appendix B).
6.1.10 After the location of the source is determined, monitor whether the source is damaged, exposed, leaking, and whether the collimation port of the source container is closed.
6.2 Source feature recognition
6.2.1 Obtain the source nuclide type, ray type and activity size through measurement, and judge and confirm the characteristic information of the source.
6.2.2 For gamma sources, portable high-purity germanium gamma spectrometers are generally used for nuclide identification and semi-quantitative or quantitative analysis of the source. It can also be based on gamma radiation
The air absorbed dose rate results estimate the activity of the source (see Appendix C).
6.2.3 When the portable high-purity germanium gamma spectrometer cannot identify the nuclide characteristics of the source, the alpha/beta surface contamination meter should be used to identify and confirm the alpha/beta source.
Recognition, use the neutron radiation monitor to identify and confirm the neutron source.
6.3 Environmental pollution monitoring
6.3.1 According to the investigation conclusion of 5.2.1, select appropriate monitoring instruments to measure the accident site and surrounding environment.
The polluted air, soil, water and other environmental media are sampled and analyzed, and the monitoring results are compared with historical data or monitoring data at reference points
Compare, analyze the level and scope of environmental pollution.
6.3.2 γ plane pollution sources can analyze the level and scope of environmental pollution by means of radiation imaging.
6.3.3 In order to grasp the level, scope and change trend of environmental pollution after the accident, it is generally necessary to expand the scope of monitoring.
Monitoring is carried out in the dispersed direction, and continuous tracking and monitoring of the environment that may or have been polluted will be carried out until the environmental pollution is controlled and restored to the background.
Level or meet the requirements of relevant standards.
6.4 Personnel pollution monitoring
6.4.1 Personal surface monitoring
6.4.1.1 Emergency personnel should conduct personal surface monitoring before entering and leaving the accident site, usually by direct measurement method (see attached
Record D), focus on measuring the exposed parts of the feet, hips, elbows, hands, face and hair.
6.4.1.2 Surface contamination monitoring should be carried out on personal items that may be contaminated, including watches, wallets and personal dosimeters. If
If personal items are found to be contaminated, the contaminated items shall be sealed and packaged, registered and the method of disposal shall be indicated.
6.4.1.3 As far as possible, use a whole-body α/β surface pollution monitor with a sensitive window area of not less than 20 cm2 to quickly carry out personal surface monitoring.
6.4.1.4 The monitoring area of the human body surface is generally 100 cm2 for skin and clothes, 30 cm2 for hands, and 3 cm2 for fingers.
6.4.1.5 When a person’s body surface is polluted more than twice the natural background, he shall be regarded as a person contaminated by radionuclides, and may be further adjusted in accordance with GBZ/T 216.
Step measurement and decontamination treatment.
6.4.2 Personal internal exposure monitoring
6.4.2.1 In the event that emergency personnel ingest, inhale or infiltrate radioactive materials through wounds, personal internal exposure monitoring should be carried out.
6.4.2.2 An X/γ radiation monitor can be used to detect the γ or X-rays (including Bremsstrahlung) emitted by radioactive materials deposited in the human body (such as the thyroid).
Radiation) in vitro direct measurement; for radionuclides that do not emit gamma or X-rays (including bremsstrahlung radiation), the
Personal biological samples (including. urine, feces, breath, blood, nasal mucus, tissue samples) or physical samples (such as aerosol samples,
Surface samples) sampling and analysis.
6.5 Confirmation of environmental restoration
6.5.1 For radioactive source accidents, after the disposal of the radioactive source is completed, the recovered accident site and surrounding environment shall be monitored to confirm the environmental protection.
Whether the environment is polluted and the pollution situation.
6.5.2 For those that cause environmental pollution, after decontamination, the on-site environment should be monitored for surface pollution to confirm that the reading is less than that specified in GB 18871
Table B11 shows the control level of radioactive surface contamination. At the same time, sample and analyze the environmental media in the contaminated area to confirm the site and surrounding environment
The environmental radiation level is already at the environmental radiation background level or meets the requirements of relevant standards.
6.5.3 On-site emergency personnel and the tools and equipment used should be monitored for surface contamination. Once contaminated, decontamination should be carried out in time.
Work until it is confirmed that the decontamination is completed.
7 Sampling and analysis
7.1 Sampling points
7.1.1 Unless it has been confirmed that the source of the accident is a radioactive source and has not been damaged or polluted the environment, the
The air, soil, water and other environmental media are sampled for total alpha, total beta and nuclide measurement and analysis. Sampling control points should be set up, and radiation protection should be considered
And sampling feasibility, with as few samples as possible to characterize the on-site environmental conditions.
7.1.2 In the event of radioactive material dispersion accidents, atmospheric sampling and analysis shall be carried out. The layout of sampling points should be centered on the accident site,
The wind direction shall be arranged in fan-shaped or circular patterns at certain intervals; it must be arranged at sensitive points such as residential areas or crowd activity areas that may be
For sampling points, attention should be paid to changes in wind direction during sampling, and the position of sampling points should be adjusted in time.
7.1.3 Attention should be paid to the risk or impact of accidents on the on-site drinking water source pollution, and to the drinking water sources and terminal drinking water sources that may be affected.
Use water to measure total alpha and total beta, and perform nuclide analysis if abnormal.
7.1.4 For on-site contaminated soil or ground, the sampling points should be arranged centered on the accident site, and the points should be arranged in a fan-shaped or circular shape at a certain interval.
According to the characteristics of the pollutants, samples are taken at different depths, while control samples are collected, and biological samples are collected around the site when necessary. Soil or ground
The gamma nuclide contamination monitoring of the table is measured by a portable high-purity germanium gamma spectrometer according to HJ 1129.
7.1.5 The gamma nuclide pollution monitoring of environmental samples shall be implemented with reference to HJ 1127.
7.2 Sample collection
7.2.1 Draw up a sampling plan according to the emergency monitoring plan, and make adjustments according to the accident scene when necessary.
7.2.2 The sample collection should be fast, and parallel double samples should be collected according to a certain proportion. If necessary, use the gamma radiation level or the surface contamination level on the sample
Perform screening.
7.2.3 According to the possibility of environmental impact caused by the accident, the sampling sequence shall be arranged. If there is air or water diffusion, air
Or water sampling in order to determine the characteristics, location, direction of pollutants and the degree of environmental pollution;
Sampling of media (such as sediment, surface soil, etc.).
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