GBZ 128-2002 Occupational external radiation personal monitoring specification
Some standard content:
Ics13.100
National Occupational Health Standard of the People's Republic of China GBZ128-2002
Specifications of Individual Monitoringfor Occupational External ExposurePromulgated on April 8, 2002
Ministry of Health of the People's Republic of China
Implementation on June 1, 2002
Normative Reference Documents
Terms and Definitions
Monitoring Methods
Personal Dosimeter
Dose Evaluation
Quality Assurance
Records, Files and Reports
Appendix A (Normative Appendix)
And Reports
Records of Individual Monitoring of External Exposure of Radiation Workers 2
This standard is formulated in accordance with the Occupational Disease Prevention and Control Law of the People's Republic of China. In case of any inconsistency between the original standard GB5294-2001 and this standard, this standard shall prevail. Article 4.1, Article 4.2 and Chapter 9 of this standard are mandatory contents, and the rest are recommended contents.
This standard was drafted mainly based on the Ministry of Health Order No. 52 "Regulations on Health Management of Radiation Workers", and referred to the relevant contents of ICRP Publication No. 60 "International Radiological Protection 1990 Recommendations", ICRP Publication No. 75 "General Principles of Radiological Protection of Workers" and IAEA Safety Series No. 115 "International Basic Safety Standards for Protection against Ionizing Radiation and Safety of Radiation Sources".
Appendix A of this standard is a normative appendix.
This standard is proposed and managed by the Ministry of Health.
The drafting unit of this standard: Institute of Radiation Protection and Nuclear Safety Medicine, Chinese Center for Disease Control and Prevention.
The main drafters of this standard: Cheng Ronglin, Wang Jianchao. This standard is interpreted by the Ministry of Health.
—Scope
Specification for personal monitoring of occupational external exposure
GBZ128-2002
This standard specifies the basic requirements for the principles, methods, dose evaluation and quality assurance of personal monitoring of external exposure in occupational exposure (hereinafter referred to as \occupational external exposure\). This standard applies to personal monitoring of occupational external exposure of radiation workers. Normative reference documents
The clauses in the following documents become the clauses of this standard through reference in this standard. For all dated referenced documents, all subsequent amendments (excluding errata) or revisions are not applicable to this standard. However, the parties who reach an agreement based on this standard are encouraged to study whether the latest versions of these documents can be used. For all undated referenced documents, the latest versions shall apply to this standard. GBZ/T151 Principles for estimating personal external exposure doses in radiation accidents 3 Terms and definitions
The following terms and definitions apply to this standard. 3.1
Occupational exposureoccupationalexposureAll exposures received by workers during work, except for those excluded by national regulations and standards and those caused by practices or sources that have been exempted. 3.2
Individual monitoringindividualmonitoringMeasurements made by workers using dosimeters worn by workers, or measurements of the types and activities of radionuclides in their bodies or excreta, and the interpretation of the measurement results. 3.3
Minimum detectable level (MDL)minimum detectable levelIn radiation monitoring, the value of a statistic used to evaluate detection capability, which refers to the minimum sample contribution that can be detected (detected) by a measurement method under a given confidence level and is different from zero. 3.4
Abnormal exposureabnormalexposure
When radiation sources are out of control, workers or members of the public are exposed to exposure that may exceed the dose limits set for them under normal circumstances. Abnormal exposure can be divided into accidental exposure and emergency exposure. 3.5
reference levelreference level
The level specified for deciding to take certain actions. A reference level can be established for any quantity that can be measured in radiation protection practice. When this level is reached or exceeded, some corresponding action should be taken. This action can be to record and archive the measured values, or to conduct further investigation or even intervention. The corresponding reference levels are called record level, investigation level4
and intervention level.
notionaldosenotionaldose
In personal monitoring, when the dosimeter worn by the worker is lost or the reading cannot be obtained for some reason, other methods are used to assign the dosimeter the dose estimate it deserves.
4 General
4.1 Monitoring principles
4.1.1 Any radiation work unit should be responsible for arranging occupational exposure monitoring and evaluation according to the specific circumstances of the practice and source it is engaged in. The evaluation of occupational exposure should be mainly based on personal monitoring of external exposure. a) Any worker who works in a controlled area, or occasionally enters a controlled area and may be exposed to significant occupational external radiation, or whose annual effective dose of occupational external radiation may exceed 5mSv/a, should be subject to personal external radiation monitoring. b) For workers who work in a supervised area or occasionally enter a controlled area and whose annual effective dose of occupational external radiation is expected to be within the range of 1mSv/a-5mSv/a, personal external radiation monitoring should be carried out as much as possible. c) For workers whose annual dose level of occupational external radiation may always be lower than the corresponding specified value in regulations or standards, personal external radiation monitoring may not be carried out.
4.1.2 All individuals engaged in or involved in radiation work should be subject to personal occupational external radiation monitoring. 4.2 Quantity to be monitored
The quantity to be measured in personal occupational external radiation monitoring is the personal dose equivalent H (d), where d refers to the depth below a specified point on the human body surface. According to the different values of d, H, (d) can be divided into: aH, (0.07), which is applicable to organs or tissues 0.07mm below the body surface, mostly used for skin. bH (3), applicable to organs or tissues 3 mm below the body surface, mostly used for the lens of the eye cH (10), applicable to organs or tissues 10 mm below the body surface, and under certain conditions, also applicable to effective dose assessment. 4.3 Monitoring Types
4.3.1 Routine Monitoring
Routine monitoring is a type of monitoring conducted at a predetermined location and at a predetermined monitoring cycle to determine whether working conditions are suitable for continued operation. Routine monitoring is related to continuous operation. This type of monitoring is to indicate working conditions including personal dose levels and satisfaction with the site stay. It is also to meet regulatory requirements. The period of routine monitoring should take into account many factors such as the nature of the work of radiation workers, the size of the dose received, the degree of dose change, and the performance of the dosimeter. The routine monitoring cycle is generally 1 month, which can be extended or shortened depending on the specific situation, but the maximum shall not exceed 3 months.
4.3.2 Task-related Monitoring
Task-related monitoring is a type of monitoring that provides immediate decision support data on operations and management for specific operations. It can also prove whether the operation is in the best state. 4.3.3 Special Monitoring
Special monitoring is a type of monitoring conducted over a limited period of time to clarify a specific problem. Special monitoring is essentially an investigation and is often used when there is a lack of information on whether workplace safety is effectively controlled. This type of monitoring is intended to provide detailed information to clarify any problems and define future procedures. 4.4 Monitoring Procedures
a) Development of a monitoring plan, especially specifying the type and scope of monitoring: b) Selection of monitoring methods;
c) Preparation of monitoring instruments, including instrument selection, commissioning, calibration and maintenance; d) Implementation of monitoring, including interpretation and preliminary processing of monitoring data; 5
e) Calculation and evaluation of dose results:
f) Monitoring records and their preservation;
g) Comprehensive quality assurance of the above procedures. 5 Monitoring Methods
5.1 Photon Radiation
5.1.1 For single-component gamma or X-rays with known energy, the personal dose equivalent can be determined by an ordinary personal dosimeter without energy identification function.
5.1.2 When encountering the following situations, an energy-discriminating personal dosimeter should be used to measure personal dose equivalents: a) single component of unknown energy or X-rays; b) multiple components of known energy of Y or X-rays; c) multiple components of unknown energy or X-rays, 5.2 Strong penetrating radiation and weak penetrating radiation mixed radiation field 5.2.1 For strong and weak penetrating radiation mixed radiation fields where weak penetrating radiation (such as β rays and low-energy X-rays) is not obvious, generally only H (10) can be monitored.
5.2.2 For strong and weak penetrating radiation mixed radiation fields where weak penetrating radiation is obvious, a discriminating personal dosimeter that can identify the two should be used, or a body dosimeter and limb dosimeters should be used to measure H (10), H, respectively.(3) and H(0.07). 5.3 Neutron and V-ray mixed radiation field
5.3.1 Regardless of the ratio of neutron dose to dose and whether this ratio is known, in principle, a discriminatory personal dose meter that can measure neutron dose and photon dose separately should be used to measure the personal dose equivalent of neutrons and photons, and then calculate the total dose.
5.3.2 When the ratio of neutron dose to dose does not exceed 10% and the ratio is known, the photon dose can also be measured only by a photon dose meter, and then the total dose can be calculated based on the photon dose monitoring results and the ratio of the two. 5.4 Inhomogeneous irradiation
When engaged in operations that may be subject to complex and inhomogeneous irradiation, workers should wear local dosimeters (such as headband dosimeters, wrist dosimeters, finger ring dosimeters or ankle dosimeters) in addition to conventional personal dosimeters on parts of the body that may be subject to greater irradiation, or on parts of the body surface corresponding to major organs. For example, when operating sealed sources, it is necessary to wear additional finger ring dosimeters on the fingers. 5.5 Abnormal irradiation
5.5.1 In the case where the expected external exposure dose greatly exceeds the dose limit (for example, when engaged in operations or emergency operations where critical accidents may occur), workers should wear reporting personal dosimeters or accident dosimeters in addition to conventional personal dosimeters.
5.5.2 When workers are exposed to accidental or emergency irradiation, in addition to the results provided by the dosimeters they wear, the estimation of accidental doses should also refer to dose data measured by other methods, such as the \Na and 3 induced in the workers' bodies after neutron irradiation. c1, measurement data of \P in hair and woolen sweaters, or other induced radionuclides. In addition, biological dosimeters based on chromosome aberration analysis of peripheral blood lymphocytes are also valuable. For the principles of accidental dose estimation, please refer to the national occupational health standard GBZ/T151. 6 Personal dosimeter
6.1 Basic performance requirements
a) It should only respond to one or more types of radiation to be measured, and its response should not be significantly affected by environmental factors such as temperature, humidity, dust, wind, light and magnetic field, as well as operational factors such as power supply voltage fluctuations and frequency fluctuations. 6
b) It should have a wide range that can cover the monitoring range. For routine monitoring, the upper limit of the range should generally reach 1Sv; for special monitoring, the upper limit of the range should reach 10Gy.
c) When monitoring Hp (10), for common X or rays, the measured energy range should generally be as wide as 20keV-1.5MeV; for those occasions where high-energy gamma or X rays may be generated, the energy upper limit should reach 9MeV. When monitoring H,(0.07), the energy range of the measurement should be as wide as 10keV-1.5MeV.
d) It should have a sufficiently high sensitivity, or a sufficiently low detection limit. e) The error introduced by the energy response and the angular response should not exceed 30% (95% confidence level, the same below). f) The loss of cumulative dose in one monitoring cycle should not exceed 10%. g) It should have easily identifiable identification and coding. h) The dosimeter should have sufficient mechanical strength, and its size, shape, structure and weight should not affect the work of individuals.
6.2 Wearing requirements
6.2.1 For relatively uniform radiation fields, when the radiation mainly comes from the front, the dosimeter should be worn in the middle of the front of the human torso, generally in front of the left chest; when the radiation mainly comes from the back of the human body, the dosimeter should be worn in the middle of the back. 6.2.2 For situations where lead aprons are worn at work (such as hospital radiology departments), the actual effective dose of workers should usually be estimated by a dosimeter worn on the torso inside the apron. When the exposure dose may be quite large (such as interventional radiology operations), a dosimeter should be worn on the collar outside the apron to estimate the dose of the unshielded part of the human body. Only when the exposure dose is very small and personal monitoring is only for obtaining an estimate of the upper limit of the dose, the dosimeter can be worn on the chest outside the apron.
6.2.3 For short-term work and temporary entry to the radiation workplace (including visitors and maintenance personnel, etc.), direct-reading personal dosimeters should be worn, and their dose data should be recorded and preserved as required. 6.2.4 When the superior competent department carries out quality assurance activities and issues quality control personal dosimeters, radiation workers are obliged to wear them at the same location as the personal dosimeters for routine monitoring as required. 6.3 Calibration
6.3.1 Personal dosimeters should be calibrated using appropriate human models. 6.3.2 Personal dosimeters should be calibrated regularly. 6.3.3 The calibrated emissivity values of the standard source or reference radiation used for calibration should be traceable to national benchmarks or international standards.
7 Dose evaluation
7.1 Conversion from practical quantity to protective quantity
7.1.1 Radiation safety analysis or dose evaluation should be based on protective quantities such as absorbed dose DT, equivalent dose H or effective dose E. 7.1.2 In personal monitoring of occupational external exposure, the instrument response directly obtained from a series of measurements and then calibrated and calculated to obtain the personal dose equivalent Hp(d) is a practical quantity. For use in radiation safety evaluation, Hp(d) should be converted into protective quantity. 7.1.3 Conversion method
a) In the practice of monitoring Y or X radiation, when the annual exposure dose of personnel is lower than the limit of 20mSv, the personal dose equivalent H(10) obtained by personal monitoring of occupational external exposure can be considered as the effective dose value E that is neither underestimated nor overestimated. b) When the annual dose monitoring results exceed the corresponding limits of equivalent dose or effective dose, the equivalent dose H and effective dose value E of the main irradiated organs or tissues should be further estimated. At this time, the equivalent dose Hr of the main irradiated organs or tissues can be measured by multiple local dose meters, and then the effective dose E can be estimated according to the following formula: E=2W·Hr
Where:
E is the effective dose in millisieverts (mSv); W is the tissue weighting factor;
Hr is the equivalent dose of the main irradiated organs or tissues in millisieverts (mSv). 7.2 General principles of dose assessment
7.2.1 When the annual exposure dose of radiation workers is less than 5mSv, only the dose results of personal monitoring need to be recorded. 7.2.2 When the annual exposure dose of radiation workers reaches and exceeds 5mSv, in addition to recording the personal monitoring results, further investigation should be conducted.
7.2.3 When the annual exposure dose of radiation workers is greater than the annual limit of 20mSv, in addition to recording the individual monitoring results, the equivalent dose of the main exposed organs or tissues of the personnel should also be estimated: If necessary, the effective dose of the personnel should also be estimated to conduct safety assessments, identify the causes, and improve protective measures. 7.3 Principles of dose assessment under conditions of coexistence of internal and external exposure 7.3.1 The occupational exposure level of any radiation worker under normal circumstances should not exceed the following limits: a) Annual average effective dose for 5 consecutive years, 20mSv; b) Effective dose in any year, 50mSv: c) Annual equivalent dose of the eye lens, 150mSv: d) Annual equivalent dose of limbs (hands and feet) or skin, 500mSv. 7.3.2 The total dose of occupational exposure includes the dose caused by occupational external exposure during the specified period and the sum of the committed doses of internal exposure caused by the intake of radionuclides during the same period. The period for calculating the committed dose should generally be 50 years for adults and up to 70 years for children. 7.3.3 One of the following methods should be used to determine whether the effective dose limit requirements are met: a) When the annual total effective dose E calculated according to the following formula is not greater than 20mSv, it is considered not to exceed the dose limit: E=H(d)+ZejingxIjing+ejinhxIjinh.... (2) Where:
Hp(d)-personal dose equivalent of external exposure due to penetrating radiation in that year, in millisieverts (mSv); ei.in-unit intake dose of staff =The committed effective dose due to radionuclide j, in millisieverts per becquerel (mSv/Bq); Ijim - the intake of radionuclide j by the workers in that year, in becquerel (Bq); ej.in - the committed effective dose due to radionuclide j per unit inhalation by the workers, in millisieverts per becquerel (mSv/Bq); Ii.inb - the inhalation of radionuclide j by the workers in that year, in becquerel (Bq); b) The dose limit is considered not to be exceeded when the following formula is satisfied: H, (d)
Wherein:
Iy ine
ALIiing
≤1....(3)
jALIjinh
DL is the annual limit of effective dose, in millisievert (mSv);ALIj.ing is the annual limit of intake of radionuclide j by ingestion, in becquerel (Bq);ALIjinh is the annual limit of intake of radionuclide j by inhalation, in becquerel (Bq);8 Quality Assurance
8.1 Overview
8.1.1 Quality assurance is an important part of personal occupational external exposure monitoring, and quality assurance should be carried out throughout the entire process from the formulation of the monitoring plan to the evaluation of the results. 8
8.1.2 When formulating a personal occupational external exposure monitoring plan, a quality assurance plan must be formulated at the same time. The formulation of a quality assurance plan should generally consider:
a) A sound personal monitoring and quality assurance organization; b) The application and maintenance of standard methods, standard instruments, standard materials and reference radiation; ) The performance and quality of instruments and devices, and their regular calibration and regular maintenance; d) Quality control measures for each link in the monitoring process; e) The value of the monitoring result must be traceable to the national benchmark and meet the uncertainty requirements; f) The selection and training of technical personnel.
8.1.3 The superior department in charge of personal occupational external exposure monitoring should: a) Plan and systematically train the technical personnel responsible for the personal occupational external exposure monitoring unit on the basic knowledge and basic skills of personal external exposure monitoring, and allow them to take up their posts only after they have passed the assessment. 。 b) Formulate and implement a verification system to check whether the monitoring unit has a quality assurance plan and the implementation of the quality assurance plan.
8.1.4 The unit implementing occupational external radiation personal monitoring should: a) Set up (deploy) a corresponding quality assurance management organization or personnel, and have them be responsible for quality assurance work. b) Regularly carry out publicity and education on occupational external radiation personal monitoring and the correct use of personal dosimeters for occupational exposed personnel who receive external radiation personal monitoring. 8.1.5 In addition to quality assurance management personnel, all personnel in each link of the monitoring process should attach importance to and do a good job in quality assurance of occupational external radiation personal monitoring. 8.2 Quality control of personal dosimeters
8.2.1 In addition to meeting the basic performance requirements of Article 6.1 of this standard, personal dosimeters should also meet other corresponding requirements specified in national standards.
8.2.2 During monitoring, a control dosimeter that can provide background data should be used. 8.2.3 During monitoring, a quality control dosimeter should be used to ensure the accuracy and reliability of the monitoring results. 8.2.4 Detectors as components of personal dosimeters should: a) have good tissue equivalence, otherwise appropriate materials should be configured to make them tissue equivalent b) have good stability and repeatability. c) be screened before each monitoring is implemented, and can only be used after passing the screening. 8.3 Quality control of laboratories and dose measurement systems 8.3.1 Standard operating procedures for laboratory dose measurement should be formulated and strictly followed. 8.3.2 Special attention should be paid to the quality control of dose measurement systems: a) The dose measurement system should be stable and reliable.
b) Performance specifications and standard operating procedures should be prepared for each device of the dose measurement system, and its performance should be calibrated and maintained regularly; standard operating procedures should be strictly followed when the equipment is used c) The calibration value of the dose measurement system should be verified before and after each dose measurement to ensure the stability of the measurement system and the reliability of the measurement results.
d) The minimum detection level of the dose measurement system should be verified at least once a year. 8.3.3 Quality control charts should be used as much as possible to control the quality of measurements. The upper and lower warning limits and control limits of the quality control chart can generally be taken as the average value of the measured value plus and minus 2 and 3 times the standard deviation. 8.4 Quality assurance of monitoring implementation
8.4.1 Standard operating procedures for each link of dosimeter issuance, wearing, transportation, recovery and storage should be formulated and strictly followed.
8.4.2 Personal dosimeters should be protected from any artificial radiation during non-working hours. 8.4.3 When monitoring operations involving open radioactive sources, dosimeters should be sealed to prevent radioactive contamination. 9
After the dosimeter is recovered, it should be checked for radioactive surface contamination. If contamination is found, it should be removed in time, and a note should be added to the dose reading record to explain its impact on the measured value.
8.5 Basic requirements for uncertainty
8.5.1 Under good laboratory conditions, the uncertainty of dose measurement should be better than 10%. 8.52 For on-site measurements:
a) When the monitored dose level is close to the dose limit, the uncertainty of photon radiation should not exceed a factor of 1.5, that is, the monitored value should be consistent with the true value within a range of -33% to 50%: the uncertainty requirements for electrons and neutrons with unknown energy can be allowed to be wider.
b) When the monitored dose level is lower, the uncertainty requirements for any radiation can be further relaxed until it does not exceed a factor of 2, that is, the monitored value should be consistent with the true value within a range of -50% to 100%. 8.6 Mutual Comparison
8.6.1 The superior department in charge of occupational external exposure personal monitoring should regularly or timely organize mutual comparison of external exposure personal monitoring between laboratories of monitoring implementation units. 8.6.2 The unit responsible for external exposure personal monitoring should actively participate in mutual comparison between domestic and foreign laboratories to discover errors or problems that are difficult for the laboratory to discover, and should analyze and identify the causes and take corrective measures. 8.7 Data Processing
8.7.1 Appropriate statistical methods (such as data rounding methods, mean and standard deviation calculation and representation methods, etc.) should be used for data processing to minimize the calculation errors that may be generated and accumulated during the data processing process. 8.7.2 Attention should be paid to the correct representation of the significant figures of the measured data. The number of significant figures of the data should appropriately reflect the accuracy of the measured value.
8.7.3 The elimination of abnormal data must be cautious. The abnormal data should be eliminated by rechecking methods on site or using appropriate statistical methods. While eliminating abnormal data, the reasons for their generation should also be checked and analyzed and recorded. 9 Records, Files and Reports
9.1 Records
9.1.1 General Requirements
a) Records should be conducive to operation management, supervision by the competent department for radiation health protection, use by radiation protection and medical monitoring, and inquiry by staff. b) The records should include monitoring plans, pretreatment, measurement, calibration, personal monitoring results, quality assurance and evaluation methods, and sometimes may also include the results of workplace monitoring. c) Every operation in the entire monitoring process from the issuance of dosimeters to the evaluation of monitoring results should be recorded clearly, concisely and accurately.
d) Special attention should be paid to recording important original measurement data so that the dose can be re-estimated based on them when the dose estimation method changes in the future.
e) Workers and medical monitoring supervisors should be allowed to inquire about occupational exposure records and related information. 9.1.2 The results of personal external exposure monitoring should be recorded on a unified form. a) The classification of occupational exposure should refer to the classification method of Table A1 in Appendix A (Normative Appendix). b) Routine monitoring results should be recorded in the format of Table A2 in Appendix A (Normative Appendix). c) The results of excessive exposure received by workers due to accidents or emergencies should be recorded in the format of Table A3 in Appendix A (Normative Appendix).
9.1.3 When the personal monitoring results of occupational external exposure of workers are acceptable, their exposure conditions should be reviewed and the review results should be attached to their corresponding personal monitoring records. The review items should at least include: a) Monitoring date:
b) Overview of abnormal conditions:
c) Radiation field review results:
d) Review conclusion:
e) Signature of the reviewer.
9.1.4 When the dosimeter is lost, damaged or the reading cannot be obtained for some reason, its nominal dose should be determined as much as possible, and the nominal dose and its determination method should be recorded in the monitoring record. One of the following methods should be reasonably selected to determine the nominal dose according to the specific situation: a) Estimate the dose using the instantaneous dose recorded by the instantaneous dosimeter worn at the same time; b) Calculate the dose using the results of monitoring at the same time and place; c) Use the average dose received by colleagues doing the same work during the same monitoring period; d) Use the average dose received by the worker in the previous twelve months; e) Use an appropriate fraction of the annual management limit. 9.1.5 When the personal external exposure monitoring result of the staff is less than MDL, it can be recorded as 1/2MDL. 9.2 Files
9.2.1 All units engaged in or involved in occupational external exposure work should: a) establish personal occupational exposure monitoring files for the staff of the unit. This file is an important part of the occupational health file. Its format is shown in Table A4 in Appendix A (Normative Appendix); b) designate special personnel to be responsible for the management of the personal occupational exposure monitoring files of the radiation workers of the unit; c) provide the new employer with a copy of the personal occupational external exposure monitoring file of the staff when the staff changes their work unit:
d) consult with the radiation health protection department or the department designated by them when the staff stops radiation work, and make arrangements for the preservation of the personal occupational exposure monitoring files of the staff. 9.2.2 In addition to the personal dose records of radiation workers during normal work, the personal occupational exposure monitoring files should also include records of excessive exposure received by them under abnormal circumstances (accidents or emergencies). 9.2.3 Before the worker reaches the age of 75, the occupational exposure personal monitoring file of the radiation worker should be well preserved; after the worker stops radiation work, his/her occupational exposure personal monitoring file should be kept for at least 30 years. 9.2.4 The superior department in charge of personal monitoring has the right to inspect and access the occupational exposure personal monitoring files of grassroots radiation work units.
9.3 Report
9.3.1 After completing the monitoring task of a monitoring cycle, the unit responsible for personal occupational external exposure monitoring shall promptly send the monitoring result notification to the monitored unit. The format of the notification is shown in Table A5 in Appendix A (Normative Appendix). 9.3.2 Units at all levels (including central, provincial and regional) responsible for personal occupational external exposure monitoring shall promptly organize, summarize, calculate and analyze the data of personal occupational external exposure monitoring of radiation workers within their scope of responsibility in this year, so as to grasp the trend of changes and distribution of personal doses and collective doses. 9.3.3 Units at all levels responsible for personal occupational external exposure monitoring shall fill in the final results of personal occupational external exposure monitoring in this year in the format of Table A6 in Appendix A (Normative Appendix) and report them to the superior competent department step by step according to regulations. Abnormal situations found during monitoring shall be reported in a timely manner.
(Normative Appendix)
Records and reports of personal occupational external exposure monitoring A1 Please refer to Table A1 for the occupational classification of occupational exposure. Table A1 Occupational classification of occupational exposure
Occupational classification
Uranium mining
Uranium metallurgy
Uranium enrichment and conversion
1 Nuclear fuel cycle
2 Medical applications
3 Industrial applications
4 Natural sources
5 Defense activities
6 Others
Fuel manufacturing
Reactor operation
Fuel reprocessing
Nuclear fuel cycle research
Diagnostic radiology||t t||Dental Radiology
Nuclear Medicine
Radiotherapy
Industrial Irradiation
Industrial Nondestructive Testing
Luminous Paint Industry
Radioisotope Production
Accelerator Operation
Civil Aviation
Coal Mining
Other Mineral MiningbZxz.net
Petroleum and Gas Industry
Mineral and Ore Processing
Nuclear Ships and Support Equipment
Other Defence Activities
Veterinary Medicine
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