GBZ 143-2002 Standard for Radiation Protection of Container Inspection Systems
Some standard content:
ICS13.100
National occupational health standard of the People's Republic of China GBZ143-2002
Radiological protection standard for container inspection system Issued on April 8, 2002
Ministry of Health of the People's Republic of China
Implementation on June 1, 2002
1 Scope
2 Normative references
3 Inspection systems and their classification
4 Radiation control level of inspection systems and their workplaces 5 Requirements for zoning of inspection sites and restriction of personnel activities 6 Radiation safety requirements for inspection systems
7 Requirements for safe operation of inspection systems
8 Radiation protection monitoring
9 Appendix A (Normative Appendix) Items and cycles of radiation protection monitoring for container inspection systems 10 Appendix B (Normative Appendix) Methods for radiation protection monitoring for container inspection systems Foreword
This standard is formulated in accordance with the Occupational Disease Prevention and Control Law of the People's Republic of China. Chapters 4 to 8 and Appendix A of this standard are mandatory contents, and the rest are recommended contents. The container inspection system is a device that uses X-rays and Y-rays to inspect containers, etc. This standard aims to standardize the radiation health protection of the container inspection system and its operation, and to ensure the safety of practitioners and the public. This standard refers to the relevant contents of the American standard ANSIN43.3 "General requirements for radiation safety of equipment equipped with non-medical X-rays and sealed y sources (<10MeV)", and is compiled in combination with the actual situation of my country's container inspection system and its operation. Appendix A and Appendix B of this standard are normative appendices. This standard is proposed and managed by the Ministry of Health.
The drafting units of this standard: Institute of Radiation Medicine, Shandong Academy of Medical Sciences, Tsinghua University, Tsinghua University Nuclear Energy Technology Design Institute, Tsinghua Tongfang Nuclear Technology Co., Ltd. The main drafters of this standard: Hou Jinpeng, Li Junli, Zhou Liye, Deng Daping, Zhu Jianguo, Liu Yisi, Gui Liming, etc.
This standard is interpreted by the Ministry of Health.
Radiation Health Protection Standard for Container Inspection System GBZ143-2002
1 Scope
This standard specifies the radiation health protection requirements and related monitoring requirements for various types of container inspection systems (hereinafter referred to as inspection systems), such as radiation control levels, inspection site zoning, radiation safety and safe operation. This standard applies to the inspection of containers or air pallets, transport trucks, freight trains, etc. and the goods they carry using Y rays or X rays below 10MV. This standard does not apply to corresponding computer tomography inspections. 2 Normative References
The clauses in the following documents become 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, parties to 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. GB4075 Classification of sealed radioactive sources
GB4076 General provisions for sealed radioactive sources
GB7465 High-activity cobalt-60 sealed radioactive sources
GB11806 Regulations for safe transportation of radioactive materials GBZ135 Standard for sanitary protection of sealed Y-radioactive source containers 3 Inspection system and its classification
3.1 Inspection system
Mainly composed of radiation source, detector, control, image analysis, safety interlock, warning and emergency facilities.
3.2 Classification of inspection system
3.2.1 Classification by radiation source used
a) Accelerator inspection system. A system that uses X-rays (less than 10MV) generated by an accelerator to inspect containers and other goods.
b) Radionuclide source inspection system. A system that uses Y-rays released by radionuclide sources (hereinafter referred to as radioactive sources) to inspect containers and other goods. c) X-ray machine inspection system. A system that uses X-rays generated by an X-ray machine to inspect containers and other goods.
3.2.2 Classification by inspection method
a) Fixed inspection system. An inspection system installed at a fixed position in a permanent building. In the inspection hall, the goods to be inspected are subjected to radiation inspection when they pass through the collimated main beam area of the system along the track. b) Mobile inspection system. An inspection system in which the radiation source and detector system synchronously move along the object to be inspected at a uniform speed for scanning. Mobile inspection systems are now divided into vehicle-mounted mobile inspection systems and combined mobile inspection systems. The former inspects the object to be inspected in a site that is circled according to the radiation dose control level and restricts the entry of unrelated personnel; the latter's radiation source and detector are installed in the inspection hall of a detachable shielding body to inspect the object to be inspected, and the control and image analysis devices are located outside the inspection hall. 4 Radiation control level of inspection systems and their workplaces 4.1 Leakage radiation level of radiation source box
The radiation source box includes a radiation source, a radiation source shielding body and assembly, and a primary collimator. The radiation source box may also include a shutter and a source device in a non-detection working state. The leakage radiation level of different types of radiation source boxes is controlled as follows:
4.1.1 Leakage radiation level of accelerator radiation source box When a shielding body of sufficient thickness is placed at the beam outlet, in the area outside the useful beam, the relative ratio of the air kerma rate at meters away from the accelerator target to the air kerma rate at 1 meter away from the target on the central axis of the useful beam without a shielding body is the radiation leakage rate of the radiation source box. The fixed inspection system should be less than 1%o: the mobile inspection system should be less than 0.1%o.
4.1.2 Leakage radiation level of the radiation source box
The leakage radiation level of the radiation source box should meet the requirements of Table 1. Table 1
Control value of air kerma rate of radiation leakage outside the radiation source box (uGy·h\) Inspection system type
Fixed system
Mobile system
5cm from the outer surface of the radiation source box
4.1.3 Radiation level of X-ray tube head assembly leakage 100cm from the outer surface of the radiation source box
Radiation air kerma rate at 1m from the focus of the X-ray tube, the fixed inspection system should not be greater than 5000μGy·h, and the mobile inspection system should not be greater than 20μGy·h\. 4.2 Radiation level of accelerator modulator leakage
The air kerma rate at 5cm from the surface of the modulator assembly should not be greater than 40uGy·h. 4.3 The radiation level of radiation source storage container leakage should comply with the requirements of Table 1 "Radiation level on the outer surface of sealed Y radioactive source container" in Article 4.1 of GBZ135 and Article 5.5.
4.4 Radiation level at the site outside the inspection system building The air kerma rate at 30cm from the outer surface of the wall of the inspection hall of the fixed inspection system should not exceed 2.5uGy·h-. For the combined mobile inspection system, the air kerma rate at 30cm from the outer surface of the shielded wall in the area of main beam irradiation should not exceed 10uGy·h. The air kerma rate at 30cm from the outer surface of the shielded wall in the non-main beam irradiation area and at the railing outside the entrance and exit doors should not exceed 2.5uGy·h-. 4.5 Radiation level of the vehicle-mounted mobile inspection site The air kerma rate at the guardrail boundary should not exceed 2.5uGy·h. The inspection system product documentation should give the minimum distance requirements between the radiation source and the four perimeters of the guardrail boundary. The air kerma rate of the control and image analysis room of the mobile inspection system installed on a vehicle should not exceed 2.5uGy·h. 5 Inspection site zoning and personnel activity restriction requirements 5.1 Inspection site zoning
5.1.1 Control area
The control area of various inspection systems is divided as follows: a) In fixed inspection systems, the area bounded by the entrance and exit doors of the inspection channel, including the radiation source room, inspection channel and detector room.
b) In combined mobile inspection systems, the area surrounded by partition walls and entrance and exit doors c) In vehicle-mounted mobile inspection systems, the area where the air kerma rate may be greater than 40uGy·h, such as the area near the radiation source and detector, and the detection area between the radiation source and detector. 5.1.2 Supervision area
The supervision area of various inspection systems is divided as follows: a) In fixed inspection system buildings, the area directly adjacent to the radiation source room, inspection channel and detector room.
b) In combined mobile inspection systems, the area between the entrance and exit doors and the railings. c) In vehicle-mounted mobile inspection systems, the area within the guardrails except the control area, the air kerma rate at any position on the guardrails is not greater than 2.5uGy·h. The control and image analysis room of a mobile inspection system installed on a vehicle belongs to the supervision area. 5.2 Requirements for personnel activity restrictions
The following restrictions are imposed on personnel activities when the inspection system is in operation: a) No personnel may enter the control area.
b2 No irrelevant personnel may enter the supervision area. c) Unless required for testing, personnel should stay outside the supervision area. 6 Inspection system radiation safety requirements
6.1 General principles
The radiation safety design of the inspection system should follow the principle of fail-safety, set up redundant and multiple safety devices, and pay attention to the use of diverse components to ensure that when a component or system fails, the inspection system can establish a safe state.
6.2 General safety requirements
6.2.1 Safety interlocks
The safety interlock settings and functions shall comply with the following:
a) The inspection system must be equipped with the following two independent safety interlocks: one is the main console key switch interlock, which means that only when the key is inserted and in the "working" position, the accelerator and X-ray machine can emit X-rays and the shutter of the radiation source inspection system can be opened; the other is the safety interlock facilities that can effectively prevent personnel from accidentally entering the control area under the detection state, such as the entrance and exit doors of the fixed inspection system channel, the railings outside the combined mobile inspection system door, the radiation source room door and other related facilities. b) If any safety interlock is opened, the inspection system shall be immediately interrupted and can only be restarted by resetting on the spot.
c) When the interlock fails, the inspection system shall be prohibited from running or interrupted, and the operation shall be displayed on the console.
6.2.2 Warning device
The setting and function of the warning device shall comply with the following:
a) The inspection channel and entrance and exit of the inspection hall of the fixed inspection system, the entrance and exit of the combined mobile inspection system and the scanning vehicle of the mobile inspection system are all equipped with light indication signals, which use different colors to indicate the immediate state of the inspection system in which it is ready to emit beam, emit beam and wait for shutdown. b) At the corresponding position of a) above, there should be an audible alarm signal for the beam emission of the detection system, which should be activated before the radiation source emits beam, and the warning time shall not be less than 5 seconds. During the entire radiation period, the signal should be continuously activated and remain stable. After the scanning is completed, the alarm bell or warning light can only stop after a certain period of time. During the combined mobile and vehicle-mounted mobile inspection, when someone mistakenly enters the radiation area inside the guardrail, an audible alarm will be sounded on the scene and in the control vehicle.
c) Outside the boundary line of the control area and outside the doors of the radiation source room and detector room of the inspection system, ionizing radiation hazard signs and clearly visible warning signs must be set. A conspicuous warning sign with the words "Beware of ionizing radiation" should be set outside the boundary of the supervision area to prevent unauthorized personnel from entering. 6.2.3 Monitoring and communication devices
The settings and functions of monitoring and communication devices should comply with the following: a) Video and display devices for monitoring must be set up to verify the presence of personnel in each area and the operating status of equipment.
b) The computer screen in the main control room should be able to display the working status of the safety interlock, should indicate a clear emergency warning signal and be able to display the content of the fault in a timely manner. c) Appropriate communication devices should be equipped between the inspection channel, radiation source room, control room and on-site staff.
6.2.4 Emergency help device
The settings and functions of the emergency help device should comply with the following: a) The inspection system should be equipped with a clearly marked and easily accessible emergency help device that can immediately interrupt radiation exposure in an emergency.
b) Emergency assistance devices should be installed in: the radiation source room, detector room, both sides of the inspection passage, the entrance and exit of the inspection hall and both sides and entrance and exit of the combined mobile inspection hall of the fixed inspection system; the outside of the scanning vehicle of the mobile inspection system or on the radiation source box or detector cross arm and on the main control console panel of various inspection systems.
c) Once the emergency assistance device is used, the inspection system cannot be restarted and emit beams unless it is reset on the spot.
6.2.5 Other requirements
For example:
a) The radiation source room of the fixed inspection system should have necessary ventilation devices. b) The inspection system site must be equipped with appropriate emergency protection equipment, such as a manual closing device in case of shutter control failure.
c) The inspection system should be equipped with complete fire prevention facilities. 6.3 Additional safety requirements for X-ray radiation sources 6.3.1 When the radiation generating device is not high-voltage, the accelerator and X-ray tube should not generate X-rays. X-rays can only be generated when all control conditions are met. 6.3.2 The beam emission of the accelerator and the X-ray machine must meet the following conditions at the same time: the interlock key is inserted in the corresponding position and all safety interlock devices are in normal state. 6.3.3 When the dose monitoring system confirms that the accelerator output dose rate exceeds the specified limit, the inspection system should terminate the beam emission.
6.3.4 The grounding fault should not cause the X-ray inspection system to generate X-rays. 6.4 Additional safety requirements for radioactive sources
6.4.1 The level of sealed radioactive sources should meet the requirements of GB4075 or GB7465 according to the activity of sealed radioactive sources. The performance of sealed radioactive sources should comply with the provisions of GB4076. 6.4.2 The radiation source room of the fixed inspection system, the combined mobile inspection hall, the storage warehouse for special vehicles for mobile inspection, etc. should be equipped with fire prevention and anti-theft facilities. 6.4.3 The inspection system shutter can only be opened when the power is on; when the power is off, the shutter is automatically closed. 6.4.4 The radiation source room door and the source operation box door can only be opened when the shutter is closed. 7 Inspection system safety operation requirements
7.1 General requirements
7.1.1 Before starting the radiation source device every day, the safety interlock, monitoring and warning devices must be carefully checked to confirm that they are in normal condition.
7.1.2 Personnel who may enter the supervision area must wear personal dosimeters. When personnel are preparing to enter the inspection channel, radiation source room, detector room and the guardrail of the vehicle-mounted mobile inspection system, they must carry a dose alarm or dose measurement instrument.
7.1.3 Before the vehicle-mounted mobile inspection, according to the technical requirements of the inspection system, the guardrail should be used to enclose the work area as the boundary of the supervision area, and necessary warning signs should be set up at the entrance and exit and the boundary. When the inspection system is started, the air kerma rate at any position on the guardrail should be tested and verified by an instrument, and it should meet the requirements of Article 4.5 of this standard.
7.1.4 After the vehicle carrying the container enters the inspection preparation area, the inspector (guide) directs the vehicle to be inspected to its position and guides the driver to exit. And only after confirming that there are no people in the inspection control area can a confirmation signal be sent to the main control room to start the radiation source. During the operation of the inspection system, the inspector should carefully control the boundaries of the supervision area.
7.1.5 When the inspection system is ready to start and in operation, the operator in the main control room should pay close attention to the console and monitor so that when an abnormal situation is found, the radiation source can be shut down or shut down in time to prevent accidents. 7.1.6 For vehicle-mounted mobile inspection systems, after the daily operation is completed, the guide should be responsible for parking the inspection vehicle in a dedicated warehouse.
7.1.7 After the inspection system fails and shuts down in an emergency, the radiation source shall not be restarted until the cause is found and the maintenance is completed.
7.1.8 When the inspection system stops running, the person in charge of the main control room should take away the master key and keep it properly. It shall not be used without permission.
7.2 Safety operation requirements during debugging and maintenance of the inspection system 7.2.1 When the maintenance personnel enter the radiation source room, detector room and inspection channel, in addition to wearing a personal dosimeter, they must also carry a dose alarm.
7.2.2 During debugging and maintenance, the radiation source beam state should be cut off. The master key must be removed first and taken away by the debugging and maintenance personnel. After the work is completed, the key will be handed over to the operator in the main control room. 7.2.3 When the safety interlock must be released during debugging and maintenance, the person in charge must agree and notify the relevant personnel. After the work is completed, the safety interlock must be restored first and the system must be used after it is confirmed to be normal. 7.3 Special requirements for the use of sealed radioactive sources
7.3.1 After the inspection system work is completed, the radiation source position and shutter status must be checked with a radiation dosimeter. 7.3.2 The transportation of sealed radioactive sources should comply with the relevant requirements of GB11806. 7.3.3 The replacement of the radioactive source of the inspection system should be carried out under the approval and supervision of the local radiation health protection department. When transferring radioactive sources from transport containers to source containers or from source containers to transport containers, auxiliary equipment that facilitates transfer operations and devices with a certain shielding effect must be used. The dose received by operators during a source replacement process should not exceed 500μSv.
7.3.4 The replaced retired radioactive sources should be recovered by the radioactive source supplier or processed or disposed of in accordance with relevant national regulations.
8 Radiation protection monitoring
8.1 Monitoring items and methods
See Appendix A (Normative Appendix) for monitoring items and cycles. The evaluation indicators shall be implemented in accordance with the relevant contents of Articles 4.1, 4.2, 4.3, 5.1 and 7.2 of this standard. See Appendix B (Normative Appendix) for monitoring methods. 8.2.Acceptance monitoring
Acceptance monitoring should include:
a) The manufacturer must monitor the radiation protection performance of the inspection system before the product leaves the factory. The monitoring items are shown in Appendix A (Normative Appendix).
b) After the inspection system is installed, the user unit shall conduct self-acceptance testing in accordance with Appendix A (Normative Appendix): c) Before the inspection system is officially used, the radiation health technical service agency recognized by the provincial and municipal health administrative departments where the user unit is located shall assign professional and technical personnel to conduct acceptance monitoring and inspection of the inspection system and protection facilities. It can only be put into use after the monitoring is qualified. Acceptance monitoring should also include: the user unit's emergency plan, emergency facilities and equipped radiation detection equipment. 8.3 Routine monitoring and inspection
8.3.1 The radiation health technical service agency recognized by the health administrative department shall conduct routine inspections of manufacturers and users once a year according to the items listed in Appendix A (Normative Appendix). The measuring instrument model and inspection results should be recorded in detail.
8.3.2 The user unit shall conduct radiation protection testing and safety inspections according to the items and inspection cycles listed in Appendix A (Normative Appendix) to eliminate hidden dangers in a timely manner and prevent accidents. The measuring instrument model and inspection results shall be recorded in detail.
8.4 Special monitoring
8.4.1 Change monitoring
When the structure, shielding, operation, inspection area and personnel residence in the adjacent area of the inspection system are changed, it shall be monitored and re-evaluated by professional and technical personnel assigned by the radiation health technical service agency recognized by the health administration department. It can only continue to be used after necessary adjustments and qualified monitoring. 8.4.2 Abnormal monitoring
When the personal dose exceeds the annual dose limit, the inspection system has abnormal conditions and treatment, it shall be monitored according to the items listed in Appendix A (Normative Appendix) to find out the cause. In the event of an accident, it shall be detected and handled in a timely manner according to the radiation accident management regulations.
8.4.3 Source replacement monitoring
When replacing a radioactive source, personal dose monitoring, dose monitoring of the operating position and location, source container dose monitoring and radioactive contamination detection should be carried out. The detection results of non-fixed radioactive contamination on the outer surface of the source container should comply with the provisions of Article 5.1 of GBZ135.
8.5 Monitoring instrument requirements
The radiation directivity, radiation energy response, dose test range and anti-interference ability of radiation detection instruments for radiation dose measurement should be suitable for detecting and measuring original rays, scattered rays and leaked radiation. Radiation detection instruments should be verified or calibrated and used within their effective time. The instrument usage status should be recorded. Appendix A
(Normative Appendix)
Container inspection system radiation protection monitoring items and periodic monitoring categories
Acceptance and routine inspection
Special monitoring
List of monitoring items and periods
Radiation level of radiation source box leakage
Radiation level of accelerator modulator leakage
Radiation level of radiation source storage container leakage
Radiation level outside the building
Radiation level of vehicle-mounted mobile inspection site
Safety interlock:||tt| |Master key switch
Doors and railings
-Other facilities
Warning devices
Monitoring and communication devices
Emergency assistance devices
Fixed inspection system ventilation devices
Change monitoring
Abnormal monitoring
Source change monitoring
Detection cycle
After the site is moved
One month
One month
Three months
The radiation level of the accelerator radiation source box leakage is only monitored before assembly by the manufacturer. Appendix B
(Normative Appendix)
Clause of this standard corresponding to the radiation protection monitoring method for container inspection system
B.1 General requirements
B.1.1 Radiation protection monitoring should be carried out under the normal working state of the inspection system. B.1.2 Use the ionization chamber or cumulative dose meter method calibrated with known energy response. B.1.3 Monitoring should be carried out at the specified measuring points and on an area with a cross-section of not less than 100cm2. B.1.4 The maximum value of the test results at each point is required to comply with the relevant provisions of this standard. B.1.5 The monitoring of safety interlocks, warning devices, emergency assistance devices and ventilation devices shall be carried out in accordance with the requirements of the inspection system product manual.
B.2 Radiation leakage level of accelerator and X-ray radiation source box B.2.1 Detection conditions: Use radiation attenuation shielding components that comply with 4.1.1 and 4.1.4 of this standard to block the outlet of the X-ray source assembly. Use rated working conditions and the conditions of maximum working tube voltage and maximum continuous working tube current respectively.
B.2.2 Detection instruments: X, Y dosimeters, X, Y patrol meters or thermoluminescent dosimeters. B.2.3 Detection position: According to Figure B1, 14 points are measured on the spherical surface 1 meter away from the accelerator target and the X-ray tube focus.
Figure B1 Leakage radiation level measurement points and ground projection diagram B.3 Leakage radiation level of radioactive source box
B.3.1 Detection conditions: Shutter on the radioactive source box is closed. B.3.2 Detection instrument: X, Y survey meter
B.3.3 Detection position: Detect at 42 points marked in Figure B2 at six different positions 5cm and 1m away from the surface of the radioactive source box.
Storage position (front, top surface) Working position
(side)
Figure B2 Schematic diagram of test position of leakage radiation level of radioactive source box All intersections of lines in the figure represent test positions B.3.4 Data processing: Multiply the monitoring result by the ratio of the rated activity of radioactive nuclides to the activity during monitoring, and convert it into the result under the rated activity of radioactive nuclides. B.4 Leakage radiation level of accelerator modulator
B.4.1 Detection conditions: When the inspection system is working normally. B.4.2 Detection instrument: X, Y patrol meter.
B.4.3 Detection position: Patrol measurement at 5 cm from the surface of the modulator cabinet. B.5 Radiation level of leakage from radioactive source storage container B.5.1 Detection conditions: The radioactive source is located in the storage container. B.5.2 Detection instrument: X, Y patrol meter.
B.5.3 Detection position: Patrol measurement at 5 cm from the surface of the storage container; measurement at 100 cm from the surface of the storage container, and 14 points on the spherical surface 1 meter away from the storage container. The measurement point position is set according to Figure B1. B.6 Radiation level in places outside buildings
B.6.1 Monitoring scope: Inspection hall of fixed inspection system and shielded body environment of combined mobile inspection system, and dedicated storage warehouse for vehicle-mounted mobile inspection system. B.6.2 Monitoring conditions: When the inspection system is working normally. B.6.3 Monitoring instrument: X, Y environmental radiation dosimeter. B.6.4 Monitoring location: Patrol at 30cm outside the wall of the inspection hall of the fixed inspection system, outside the shielding wall of the combined mobile inspection system, or outside each wall of the warehouse of the vehicle-mounted mobile inspection system. The number of selected points shall not be less than ten. For the inspection system, select three points 30cm outside the door and entrance and exit railings of the inspection hall. Note that the selected points should be evenly distributed. B.7 Radiation level at the vehicle-mounted mobile inspection site B.7.1 Monitoring conditions: When the inspection system is working normally or each time the inspection site is moved. B.7.2 Monitoring instruments: X, Y dosimeters and X, Y environmental radiation dosimeters. B.7.3 Monitoring location: Patrol along the guardrails at the boundary of the supervision area, and focus on the guardrail boundaries and the entrances and exits of the supervision area in the forward and reverse directions of the useful beam; in the direction of the useful beam, conduct necessary patrols at buildings or personnel residences within 10m from the boundary of the supervision area. B.8 Source replacement monitoring
B.8.1 Monitoring conditions: When the inspection system replaces the radiation source. B.8.2 Monitoring instruments: X, Y dosimeters, thermoluminescent dosimeters, α, β contamination detectors. B.8.3 Monitoring content: air kerma rate at the operating position, personal dose of source change personnel, radiation leakage rate and contamination status of transport containers.4 Special monitoring
8.4.1 Change monitoring bzxz.net
When the structure, shielding, operation, inspection area and personnel presence in the adjacent area of the inspection system are changed, it shall be monitored and re-evaluated by professional and technical personnel assigned by the radiation health technical service agency recognized by the health administration department. It can continue to be used only after necessary adjustments and qualified monitoring. 8.4.2 Abnormal monitoring
When the personal dose exceeds the annual dose limit, the inspection system has abnormal conditions and treatment, it shall be monitored according to the items listed in Appendix A (Normative Appendix) to find out the cause. In the event of an accident, it shall be detected and handled in a timely manner according to the radiation accident management regulations.
8.4.3 Source replacement monitoring
When replacing the radioactive source, personal dose monitoring, dose monitoring of the operating position and location, source container dose monitoring and radioactive contamination detection shall be carried out. The detection results of non-fixed radioactive contamination on the outer surface of the source container shall comply with the provisions of Article 5.1 of GBZ135.
8.5 Requirements for monitoring instruments
The radiation directivity, radiation energy response, dose test range and anti-interference capability of radiation detection instruments for radiation dose measurement should be applicable to the detection and measurement of original radiation, scattered radiation and leakage radiation. Radiation detection instruments should be verified or calibrated and used within their effective time. The instrument usage status should be recorded. Appendix A
(Normative Appendix)
Radiation protection monitoring items and cycle monitoring categories for container inspection system
Acceptance and routine inspection
Special monitoring
List of monitoring items and cycles
Radiation level of radiation source box leakage
Radiation level of accelerator modulator leakage
Radiation level of radiation source storage container leakage
Radiation level outside the building
Radiation level at the mobile vehicle inspection site
Safety interlock:||tt| |Master key switch
Doors and railings
-Other facilities
Warning devices
Monitoring and communication devices
Emergency assistance devices
Fixed inspection system ventilation devices
Change monitoring
Abnormal monitoring
Source change monitoring
Detection cycle
After the site is moved
One month
One month
Three months
The radiation level of the accelerator radiation source box leakage is only monitored before assembly by the manufacturer. Appendix B
(Normative Appendix)
Clause of this standard corresponding to the radiation protection monitoring method for container inspection system
B.1 General requirements
B.1.1 Radiation protection monitoring should be carried out under the normal working state of the inspection system. B.1.2 Use the ionization chamber or cumulative dose meter method calibrated with known energy response. B.1.3 Monitoring should be carried out at the specified measuring points and on an area with a cross-section of not less than 100cm2. B.1.4 The maximum value of the test results at each point is required to comply with the relevant provisions of this standard. B.1.5 The monitoring of safety interlocks, warning devices, emergency assistance devices and ventilation devices shall be carried out in accordance with the requirements of the inspection system product manual.
B.2 Radiation leakage level of accelerator and X-ray radiation source box B.2.1 Detection conditions: Use radiation attenuation shielding components that comply with 4.1.1 and 4.1.4 of this standard to block the outlet of the X-ray source assembly. Use rated working conditions and the conditions of maximum working tube voltage and maximum continuous working tube current respectively.
B.2.2 Detection instruments: X, Y dosimeters, X, Y patrol meters or thermoluminescent dosimeters. B.2.3 Detection position: According to Figure B1, 14 points are measured on the spherical surface 1 meter away from the accelerator target and the X-ray tube focus.
Figure B1 Leakage radiation level measurement points and ground projection diagram B.3 Leakage radiation level of radioactive source box
B.3.1 Detection conditions: Shutter on the radioactive source box is closed. B.3.2 Detection instrument: X, Y survey meter
B.3.3 Detection position: Detect at 42 points marked in Figure B2 at six different positions 5cm and 1m away from the surface of the radioactive source box.
Storage position (front, top surface) Working position
(side)
Figure B2 Schematic diagram of test position of leakage radiation level of radioactive source box All intersections of lines in the figure represent test positions B.3.4 Data processing: Multiply the monitoring result by the ratio of the rated activity of radioactive nuclides to the activity during monitoring, and convert it into the result under the rated activity of radioactive nuclides. B.4 Leakage radiation level of accelerator modulator
B.4.1 Detection conditions: When the inspection system is working normally. B.4.2 Detection instrument: X, Y patrol meter.
B.4.3 Detection position: Patrol measurement at 5 cm from the surface of the modulator cabinet. B.5 Radiation level of leakage from radioactive source storage container B.5.1 Detection conditions: The radioactive source is located in the storage container. B.5.2 Detection instrument: X, Y patrol meter.
B.5.3 Detection position: Patrol measurement at 5 cm from the surface of the storage container; measurement at 100 cm from the surface of the storage container, and 14 points on the spherical surface 1 meter away from the storage container. The measurement point position is set according to Figure B1. B.6 Radiation level in places outside buildings
B.6.1 Monitoring scope: Inspection hall of fixed inspection system and shielded body environment of combined mobile inspection system, and dedicated storage warehouse for vehicle-mounted mobile inspection system. B.6.2 Monitoring conditions: When the inspection system is working normally. B.6.3 Monitoring instrument: X, Y environmental radiation dosimeter. B.6.4 Monitoring location: Patrol at 30cm outside the wall of the inspection hall of the fixed inspection system, outside the shielding wall of the combined mobile inspection system, or outside each wall of the warehouse of the vehicle-mounted mobile inspection system. The number of selected points shall not be less than ten. For the inspection system, select three points 30cm outside the door and entrance and exit railings of the inspection hall. Note that the selected points should be evenly distributed. B.7 Radiation level at the vehicle-mounted mobile inspection site B.7.1 Monitoring conditions: When the inspection system is working normally or each time the inspection site is moved. B.7.2 Monitoring instruments: X, Y dosimeters and X, Y environmental radiation dosimeters. B.7.3 Monitoring location: Patrol along the guardrails at the boundary of the supervision area, and focus on the guardrail boundaries and the entrances and exits of the supervision area in the forward and reverse directions of the useful beam; in the direction of the useful beam, conduct necessary patrols at buildings or personnel residences within 10m from the boundary of the supervision area. B.8 Source replacement monitoring
B.8.1 Monitoring conditions: When the inspection system replaces the radiation source. B.8.2 Monitoring instruments: X, Y dosimeters, thermoluminescent dosimeters, α, β contamination detectors. B.8.3 Monitoring content: air kerma rate at the operating position, personal dose of source change personnel, radiation leakage rate and contamination status of transport containers.4 Special monitoring
8.4.1 Change monitoring
When the structure, shielding, operation, inspection area and personnel presence in the adjacent area of the inspection system are changed, it shall be monitored and re-evaluated by professional and technical personnel assigned by the radiation health technical service agency recognized by the health administration department. It can continue to be used only after necessary adjustments and qualified monitoring. 8.4.2 Abnormal monitoring
When the personal dose exceeds the annual dose limit, the inspection system has abnormal conditions and treatment, it shall be monitored according to the items listed in Appendix A (Normative Appendix) to find out the cause. In the event of an accident, it shall be detected and handled in a timely manner according to the radiation accident management regulations.
8.4.3 Source replacement monitoring
When replacing the radioactive source, personal dose monitoring, dose monitoring of the operating position and location, source container dose monitoring and radioactive contamination detection shall be carried out. The detection results of non-fixed radioactive contamination on the outer surface of the source container shall comply with the provisions of Article 5.1 of GBZ135.
8.5 Requirements for monitoring instruments
The radiation directivity, radiation energy response, dose test range and anti-interference capability of radiation detection instruments for radiation dose measurement should be applicable to the detection and measurement of original radiation, scattered radiation and leakage radiation. Radiation detection instruments should be verified or calibrated and used within their effective time. The instrument usage status should be recorded. Appendix A
(Normative Appendix)
Radiation protection monitoring items and cycle monitoring categories for container inspection system
Acceptance and routine inspection
Special monitoring
List of monitoring items and cycles
Radiation level of radiation source box leakage
Radiation level of accelerator modulator leakage
Radiation level of radiation source storage container leakage
Radiation level outside the building
Radiation level at the mobile vehicle inspection site
Safety interlock:||tt| |Master key switch
Doors and railings
-Other facilities
Warning devices
Monitoring and communication devices
Emergency assistance devices
Fixed inspection system ventilation devices
Change monitoring
Abnormal monitoring
Source change monitoring
Detection cycle
After the site is moved
One month
One month
Three months
The radiation level of the accelerator radiation source box leakage is only monitored before assembly by the manufacturer. Appendix B
(Normative Appendix)
Clause of this standard corresponding to the radiation protection monitoring method for container inspection system
B.1 General requirements
B.1.1 Radiation protection monitoring should be carried out under the normal working state of the inspection system. B.1.2 Use the ionization chamber or cumulative dose meter method calibrated with known energy response. B.1.3 Monitoring should be carried out at the specified measuring points and on an area with a cross-section of not less than 100cm2. B.1.4 The maximum value of the test results at each point is required to comply with the relevant provisions of this standard. B.1.5 The monitoring of safety interlocks, warning devices, emergency assistance devices and ventilation devices shall be carried out in accordance with the requirements of the inspection system product manual.
B.2 Radiation leakage level of accelerator and X-ray radiation source box B.2.1 Detection conditions: Use radiation attenuation shielding components that comply with 4.1.1 and 4.1.4 of this standard to block the outlet of the X-ray source assembly. Use rated working conditions and the conditions of maximum working tube voltage and maximum continuous working tube current respectively.
B.2.2 Detection instruments: X, Y dosimeters, X, Y patrol meters or thermoluminescent dosimeters. B.2.3 Detection position: According to Figure B1, 14 points are measured on the spherical surface 1 meter away from the accelerator target and the X-ray tube focus.
Figure B1 Leakage radiation level measurement points and ground projection diagram B.3 Leakage radiation level of radioactive source box
B.3.1 Detection conditions: Shutter on the radioactive source box is closed. B.3.2 Detection instrument: X, Y survey meter
B.3.3 Detection position: Detect at 42 points marked in Figure B2 at six different positions 5cm and 1m away from the surface of the radioactive source box.
Storage position (front, top surface) Working position
(side)
Figure B2 Schematic diagram of test position of leakage radiation level of radioactive source box All intersections of lines in the figure represent test positions B.3.4 Data processing: Multiply the monitoring result by the ratio of the rated activity of radioactive nuclides to the activity during monitoring, and convert it into the result under the rated activity of radioactive nuclides. B.4 Leakage radiation level of accelerator modulator
B.4.1 Detection conditions: When the inspection system is working normally. B.4.2 Detection instrument: X, Y patrol meter.
B.4.3 Detection position: Patrol measurement at 5 cm from the surface of the modulator cabinet. B.5 Radiation level of leakage from radioactive source storage container B.5.1 Detection conditions: The radioactive source is located in the storage container. B.5.2 Detection instrument: X, Y patrol meter.
B.5.3 Detection position: Patrol measurement at 5 cm from the surface of the storage container; measurement at 100 cm from the surface of the storage container, and 14 points on the spherical surface 1 meter away from the storage container. The measurement point position is set according to Figure B1. B.6 Radiation level in places outside buildings
B.6.1 Monitoring scope: Inspection hall of fixed inspection system and shielded body environment of combined mobile inspection system, and dedicated storage warehouse for vehicle-mounted mobile inspection system. B.6.2 Monitoring conditions: When the inspection system is working normally. B.6.3 Monitoring instrument: X, Y environmental radiation dosimeter. B.6.4 Monitoring location: Patrol at 30cm outside the wall of the inspection hall of the fixed inspection system, outside the shielding wall of the combined mobile inspection system, or outside each wall of the warehouse of the vehicle-mounted mobile inspection system. The number of selected points shall not be less than ten. For the inspection system, select three points 30cm outside the door and entrance and exit railings of the inspection hall. Note that the selected points should be evenly distributed. B.7 Radiation level at the vehicle-mounted mobile inspection site B.7.1 Monitoring conditions: When the inspection system is working normally or each time the inspection site is moved. B.7.2 Monitoring instruments: X, Y dosimeters and X, Y environmental radiation dosimeters. B.7.3 Monitoring location: Patrol along the guardrails at the boundary of the supervision area, and focus on the guardrail boundaries and the entrances and exits of the supervision area in the forward and reverse directions of the useful beam; in the direction of the useful beam, conduct necessary patrols at buildings or personnel residences within 10m from the boundary of the supervision area. B.8 Source replacement monitoring
B.8.1 Monitoring conditions: When the inspection system replaces the radiation source. B.8.2 Monitoring instruments: X, Y dosimeters, thermoluminescent dosimeters, α, β contamination detectors. B.8.3 Monitoring content: air kerma rate at the operating position, personal dose of source change personnel, radiation leakage rate and contamination status of transport containers.5 Requirements for monitoring instruments
The radiation directivity, radiation energy response, dose test range and anti-interference capability of radiation detection instruments for radiation dose measurement should be applicable to the detection and measurement of original radiation, scattered radiation and leakage radiation. Radiation detection instruments should be verified or calibrated and used within their effective time. The instrument usage status should be recorded. Appendix A
(Normative Appendix)
Radiation protection monitoring items and cycles for container inspection system Monitoring categories
Acceptance and routine inspection
Special monitoring
List of monitoring items and cycles
Radiation level of radiation source box leakage
Radiation level of accelerator modulator leakage
Radiation level of radiation source storage container leakage
Radiation level outside the building
Radiation level at the mobile vehicle inspection site
Safety interlock:||tt| |Master key switch
Doors and railings
-Other facilities
Warning devices
Monitoring and communication devices
Emergency assistance devices
Fixed inspection system ventilation devices
Change monitoring
Abnormal monitoring
Source change monitoring
Detection cycle
After the site is moved
One month
One month
Three months
The radiation level of the accelerator radiation source box leakage is only monitored before assembly by the manufacturer. Appendix B
(Normative Appendix)
Clause of this standard corresponding to the radiation protection monitoring method for container inspection system
B.1 General requirements
B.1.1 Radiation protection monitoring should be carried out under the normal working state of the inspection system. B.1.2 Use the ionization chamber or cumulative dose meter method calibrated with known energy response. B.1.3 Monitoring should be carried out at the specified measuring points and on an area with a cross-section of not less than 100cm2. B.1.4 The maximum value of the test results at each point is required to comply with the relevant provisions of this standard. B.1.5 The monitoring of safety interlocks, warning devices, emergency assistance devices and ventilation devices shall be carried out in accordance with the requirements of the inspection system product manual.
B.2 Radiation leakage level of accelerator and X-ray radiation source box B.2.1 Detection conditions: Use radiation attenuation shielding components that comply with 4.1.1 and 4.1.4 of this standard to block the outlet of the X-ray source assembly. Use rated working conditions and the conditions of maximum working tube voltage and maximum continuous working tube current respectively.
B.2.2 Detection instruments: X, Y dosimeters, X, Y patrol meters or thermoluminescent dosimeters. B.2.3 Detection position: According to Figure B1, 14 points are measured on the spherical surface 1 meter away from the accelerator target and the X-ray tube focus.
Figure B1 Leakage radiation level measurement points and ground projection diagram B.3 Leakage radiation level of radioactive source box
B.3.1 Detection conditions: Shutter on the radioactive source box is closed. B.3.2 Detection instrument: X, Y survey meter
B.3.3 Detection position: Detect at 42 points marked in Figure B2 at six different positions 5cm and 1m away from the surface of the radioactive source box.
Storage position (front, top surface) Working position
(side)
Figure B2 Schematic diagram of test position of leakage radiation level of radioactive source box All intersections of lines in the figure represent test positions B.3.4 Data processing: Multiply the monitoring result by the ratio of the rated activity of radioactive nuclides to the activity during monitoring, and convert it into the result under the rated activity of radioactive nuclides. B.4 Leakage radiation level of accelerator modulator
B.4.1 Detection conditions: When the inspection system is working normally. B.4.2 Detection instrument: X, Y patrol meter.
B.4.3 Detection position: Patrol measurement at 5 cm from the surface of the modulator cabinet. B.5 Radiation level of leakage from radioactive source storage container B.5.1 Detection conditions: The radioactive source is located in the storage container. B.5.2 Detection instrument: X, Y patrol meter.
B.5.3 Detection position: Patrol measurement at 5 cm from the surface of the storage container; measurement at 100 cm from the surface of the storage container, and 14 points on the spherical surface 1 meter away from the storage container. The measurement point position is set according to Figure B1. B.6 Radiation level in places outside buildings
B.6.1 Monitoring scope: Inspection hall of fixed inspection system and shielded body environment of combined mobile inspection system, and dedicated storage warehouse for vehicle-mounted mobile inspection system. B.6.2 Monitoring conditions: When the inspection system is working normally. B.6.3 Monitoring instrument: X, Y environmental radiation dosimeter. B.6.4 Monitoring location: Patrol at 30cm outside the wall of the inspection hall of the fixed inspection system, outside the shielding wall of the combined mobile inspection system, or outside each wall of the warehouse of the vehicle-mounted mobile inspection system. The number of selected points shall not be less than ten. For the inspection system, select three points 30cm outside the door and entrance and exit railings of the inspection hall. Note that the selected points should be evenly distributed. B.7 Radiation level at the vehicle-mounted mobile inspection site B.7.1 Monitoring conditions: When the inspection system is working normally or each time the inspection site is moved. B.7.2 Monitoring instruments: X, Y dosimeters and X, Y environmental radiation dosimeters. B.7.3 Monitoring location: Patrol along the guardrails at the boundary of the supervision area, and focus on the guardrail boundaries and the entrances and exits of the supervision area in the forward and reverse directions of the useful beam; in the direction of the useful beam, conduct necessary patrols at buildings or personnel residences within 10m from the boundary of the supervision area. B.8 Source replacement monitoring
B.8.1 Monitoring conditions: When the inspection system replaces the radiation source. B.8.2 Monitoring instruments: X, Y dosimeters, thermoluminescent dosimeters, α, β contamination detectors. B.8.3 Monitoring content: air kerma rate at the operating position, personal dose of source change personnel, radiation leakage rate and contamination status of transport containers.5 Requirements for monitoring instruments
The radiation directivity, radiation energy response, dose test range and anti-interference capability of radiation detection instruments for radiation dose measurement should be applicable to the detection and measurement of original radiation, scattered radiation and leakage radiation. Radiation detection instruments should be verified or calibrated and used within their effective time. The instrument usage status should be recorded. Appendix A
(Normative Appendix)
Radiation protection monitoring items and cycles for container inspection system Monitoring categories
Acceptance and routine inspection
Special monitoring
List of monitoring items and cycles
Radiation level of radiation source box leakage
Radiation level of accelerator modulator leakage
Radiation level of radiation source storage container leakage
Radiation level outside the building
Radiation level at the mobile vehicle inspection site
Safety interlock:||tt| |Master key switch
Doors and railings
-Other facilities
Warning devices
Monitoring and communication devices
Emergency assistance devices
Fixed inspection system ventilation devices
Change monitoring
Abnormal monitoring
Source change monitoring
Detection cycle
After the site is moved
One month
One month
Three months
The radiation level of the accelerator radiation source box leakage is only monitored before assembly by the manufacturer. Appendix B
(Normative Appendix)
Clause of this standard corresponding to the radiation protection monitoring method for container inspection system
B.1 General requirements
B.1.1 Radiation protection monitoring should be carried out under the normal working state of the inspection system. B.1.2 Use the ionization chamber or cumulative dose meter method calibrated with known energy response. B.1.3 Monitoring should be carried out at the specified measuring points and on an area with a cross-section of not less than 100cm2. B.1.4 The maximum value of the test results at each point is required to comply with the relevant provisions of this standard. B.1.5 The monitoring of safety interlocks, warning devices, emergency assistance devices and ventilation devices shall be carried out in accordance with the requirements of the inspection system product manual.
B.2 Radiation leakage level of accelerator and X-ray radiation source box B.2.1 Detection conditions: Use radiation attenuation shielding components that comply with 4.1.1 and 4.1.4 of this standard to block the outlet of the X-ray source assembly. Use rated working conditions and the conditions of maximum working tube voltage and maximum continuous working tube current respectively.
B.2.2 Detection instruments: X, Y dosimeters, X, Y patrol meters or thermoluminescent dosimeters. B.2.3 Detection position: According to Figure B1, 14 points are measured on the spherical surface 1 meter away from the accelerator target and the X-ray tube focus.
Figure B1 Leakage radiation level measurement points and ground projection diagram B.3 Leakage radiation level of radioactive source box
B.3.1 Detection conditions: Shutter on the radioactive source box is closed. B.3.2 Detection instrument: X, Y survey meter
B.3.3 Detection position: Detect at 42 points marked in Figure B2 at six different positions 5cm and 1m away from the surface of the radioactive source box.
Storage position (front, top surface) Working position
(side)
Figure B2 Schematic diagram of test position of leakage radiation level of radioactive source box All intersections of lines in the figure represent test positions B.3.4 Data processing: Multiply the monitoring result by the ratio of the rated activity of radioactive nuclides to the activity during monitoring, and convert it into the result under the rated activity of radioactive nuclides. B.4 Leakage radiation level of accelerator modulator
B.4.1 Detection conditions: When the inspection system is working normally. B.4.2 Detection instrument: X, Y patrol meter.
B.4.3 Detection position: Patrol measurement at 5 cm from the surface of the modulator cabinet. B.5 Radiation level of leakage from radioactive source storage container B.5.1 Detection conditions: The radioactive source is located in the storage container. B.5.2 Detection instrument: X, Y patrol meter.
B.5.3 Detection position: Patrol measurement at 5 cm from the surface of the storage container; measurement at 100 cm from the surface of the storage container, and 14 points on the spherical surface 1 meter away from the storage container. The measurement point position is set according to Figure B1. B.6 Radiation level in places outside buildings
B.6.1 Monitoring scope: Inspection hall of fixed inspection system and shielded body environment of combined mobile inspection system, and dedicated storage warehouse for vehicle-mounted mobile inspection system. B.6.2 Monitoring conditions: When the inspection system is working normally. B.6.3 Monitoring instrument: X, Y environmental radiation dosimeter. B.6.4 Monitoring location: Patrol at 30cm outside the wall of the inspection hall of the fixed inspection system, outside the shielding wall of the combined mobile inspection system, or outside each wall of the warehouse of the vehicle-mounted mobile inspection system. The number of selected points shall not be less than ten. For the inspection system, select three points 30cm outside the door and entrance and exit railings of the inspection hall. Note that the selected points should be evenly distributed. B.7 Radiation level at the vehicle-mounted mobile inspection site B.7.1 Monitoring conditions: When the inspection system is working normally or each time the inspection site is moved. B.7.2 Monitoring instruments: X, Y dosimeters and X, Y environmental radiation dosimeters. B.7.3 Monitoring location: Patrol along the guardrails at the boundary of the supervision area, and focus on the guardrail boundaries and the entrances and exits of the supervision area in the forward and reverse directions of the useful beam; in the direction of the useful beam, conduct necessary patrols at buildings or personnel residences within 10m from the boundary of the supervision area. B.8 Source replacement monitoring
B.8.1 Monitoring conditions: When the inspection system replaces the radiation source. B.8.2 Monitoring instruments: X, Y dosimeters, thermoluminescent dosimeters, α, β contamination detectors. B.8.3 Monitoring content: air kerma rate at the operating position, personal dose of source change personnel, radiation leakage rate and contamination status of transport containers.4 Monitoring location: Patrol at 30cm outside the wall of the inspection hall of the fixed inspection system, outside the shielding wall of the combined mobile inspection system, or outside each wall of the warehouse of the vehicle-mounted mobile inspection system. The number of selected points shall not be less than ten. For the inspection system, select three points 30cm outside the door and entrance and exit railings of the inspection hall. Note that the selected points should be evenly distributed. B.7 Radiation level at the vehicle-mounted mobile inspection site B.7.1 Monitoring conditions: When the inspection system is working normally or each time the inspection site is moved. B.7.2 Monitoring instruments: X, Y dosimeters and X, Y environmental radiation dosimeters. B.7.3 Monitoring location: Patrol along the guardrails at the boundary of the supervision area, and focus on the guardrail boundaries and entrances and exits of the supervision area in the forward and reverse directions of the useful beam; in the direction of the useful beam, conduct necessary patrols at buildings or personnel residences within 10m from the boundary of the supervision area. B.8 Source replacement monitoring
B.8.1 Monitoring conditions: When the inspection system replaces the radiation source. B.8.2 Monitoring instruments: X, Y dosimeters, thermoluminescent dosimeters, α, β contamination detectors. B.8.3 Monitoring content: air kerma rate at the operating position, personal dose of source change personnel, radiation leakage rate and contamination status of transport containers.4 Monitoring location: Patrol at 30cm outside the wall of the inspection hall of the fixed inspection system, outside the shielding wall of the combined mobile inspection system, or outside each wall of the warehouse of the vehicle-mounted mobile inspection system. The number of selected points shall not be less than ten. For the inspection system, select three points 30cm outside the door and entrance and exit railings of the inspection hall. Note that the selected points should be evenly distributed. B.7 Radiation level at the vehicle-mounted mobile inspection site B.7.1 Monitoring conditions: When the inspection system is working normally or each time the inspection site is moved. B.7.2 Monitoring instruments: X, Y dosimeters and X, Y environmental radiation dosimeters. B.7.3 Monitoring location: Patrol along the guardrails at the boundary of the supervision area, and focus on the guardrail boundaries and entrances and exits of the supervision area in the forward and reverse directions of the useful beam; in the direction of the useful beam, conduct necessary patrols at buildings or personnel residences within 10m from the boundary of the supervision area. B.8 Source replacement monitoring
B.8.1 Monitoring conditions: When the inspection system replaces the radiation source. B.8.2 Monitoring instruments: X, Y dosimeters, thermoluminescent dosimeters, α, β contamination detectors. B.8.3 Monitoring content: air kerma rate at the operating position, personal dose of source change personnel, radiation leakage rate and contamination status of transport containers.
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