This standard specifies the general radiation health protection requirements for the use of sealed radioactive sources. This standard does not apply to instrument calibration sources, medical sealed sources and sealed sources encapsulated in glass containers; this standard also does not apply to neutron sealed sources. GB 16354-1996 Radiation health protection requirements for the use of sealed radioactive sources GB16354-1996 standard download decompression password: www.bzxz.net

National Standard of the People's Republic of China
Radiological protection requirements for using sealed radioactive sources1 Subject content and scope of application
GB16354—1996
This standard specifies the general radiological protection requirements for using sealed radioactive sources (hereinafter referred to as sealed sources). This standard applies to sealed sources of 3.7×104~3.7×1012Bq (μCi~hCi). This standard does not apply to instrument calibration sources, medical sealed sources and sealed sources encapsulated in glass containers; this standard also does not apply to neutron sealed sources.
2 Reference standards
GB4075
Classification of sealed radioactive sources
GB4076
General provisions for sealed radioactive sources
GB4792 Basic standards for radiation health protection
GB11806 Regulations for safe transportation of radioactive materials 3 Terminology
3.1 Sealed (radioactive) sources sealed radioactive sources Radioactive sources sealed in a shell or a tight covering layer, such shell or covering layer has sufficient strength to prevent radioactive materials from leaking out under the designed conditions of use and normal wear. 3.2 Protective container Protective container Any container that can shield (or weaken) the radiation of a sealed source so that the leakage radiation level outside the container meets the corresponding standards. According to their different functions, protective containers can be divided into storage containers, transport containers and working containers. 4 Protection requirements for sealed sources
4.1 Sealed sources must meet the requirements of GB4075 and GB4076. 4.2 Before the sealed source leaves the factory or is recovered after being stolen, activity tests, leakage tests and surface radioactive contamination tests should be carried out. 4.3 The sealed source inspection certificate, arrival registration, and relevant information such as issuance and transfer certificates should be kept for a long time together with the sealed source and checked regularly.
5 Requirements for protective containers
5.1 Storage containers and transport containers must be convenient for taking and placing sealed sources. 5.2 Transport containers should be easy to carry and should be equipped with markers such as "lead seals" to prove that they have not been opened. 5.3 Working containers should be marked with the number, model, nuclide name, activity, radiation type, manufacturer, date of sale and a conspicuous "ionizing radiation" mark.
Approved by the State Administration of Technical Supervision on May 23, 1996 108
Implemented on December 1, 1996
GB16354—1996
5.4 When the sealed source is in the storage position, the corresponding dose equivalent rate limit near the working container should be determined according to different use conditions and environments to ensure that the exposure dose of the surrounding personnel does not exceed the requirements specified in GB4792. 5.5 The working container must be equipped with a source position indicator to clearly show that the sealed source is in the storage position or working position. 5.6 The working container must be equipped with a special structure to prevent the sealed source from falling off or being opened by unrelated personnel. 6 Sealed Source Storage
6.1 According to the type, quantity and total activity of the sealed source, a safe and reliable storage room, storage cabinet, storage box and other corresponding special storage equipment should be designed.
6.2 The storage room must comply with the protection and shielding design requirements of GB4792 to ensure the safety of the surrounding environment. The storage room should be managed by a dedicated person. 6.3 Some source storage rooms must be built with source pits. The protection facilities of the source pits shall be determined according to the maximum design capacity of the sealed source. The source pits shall be kept dry.
6.4 The source storage room shall be equipped with a conspicuous "ionizing radiation" sign, and unauthorized personnel shall be strictly prohibited from entering. 6.5 The source storage room shall have sufficient usable area to facilitate the storage and access of sealed sources; and good ventilation and lighting shall be maintained. 6.6 The source storage room, source storage cabinets, boxes, etc. shall have fireproof, waterproof, explosion-proof, anti-corrosion and anti-theft safety facilities. 7 Sealed source transportation
7.1 The transportation of sealed sources shall comply with the provisions of GB11806 on the safe transportation of radioactive materials. 7.2 The sealed source transportation vehicle shall not be mixed with flammable, explosive and other dangerous goods. 7.3 The sealed source transportation vehicle must be equipped with safety facilities to prevent the sealed source from being lost, overturned, scattered or stolen. 7.4 After the sealed source arrives, the user department must monitor the radiation level and dose rate of the surface contamination of the packaging box, and check whether the test results are consistent with the product certificate provided by the supplier. 8 Operation requirements www.bzxz.net
8.1 Sealed source operators and managers must receive radiation protection professional training before taking up their posts, master certain safety protection knowledge and skills, and pass the assessment.
8.2 Operators should take various effective protection measures based on the number and activity of sealed sources, according to the principle of radiation protection optimization, and fully consider factors such as time, distance, and shielding facilities to control the exposure dose to the lowest level possible. 8.3 The user department should have prevention and treatment measures for possible sealed source accidents. 8.4 Operators should use corresponding tools and shielding facilities according to their type and activity. 8.5 When the sealed source container is replaced, professional protection personnel should be responsible for on-site operation dose monitoring. 8.6 When the sealed source device is operated in the field, a certain range of control area should be provided in the direction of the useful beam projection. 8.7 The user department should conduct an inspection of the protection performance and safety facilities of the sealed source equipment at least once a year. If contamination or leakage is found, measures must be taken immediately, and the inspection results must be recorded in detail and properly stored and archived. 109
Additional Notes:
GB16354-1996
This standard was proposed by the Ministry of Health of the People's Republic of China. This standard was drafted by the Shanghai Institute of Radiological Medicine. The main drafter of this standard was Qian Zhilin.
This standard was interpreted by the Ministry of Health's Industrial Hygiene Laboratory, the technical unit entrusted by the Ministry of Health. 110
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