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GB 16360-1996 Standard for radiation health protection in clinical nuclear medicine

Basic Information

Standard ID: GB 16360-1996

Standard Name: Standard for radiation health protection in clinical nuclear medicine

Chinese Name: 临床核医学放射卫生防护标准

Standard category:National Standard (GB)

state:in force

Date of Release1996-05-23

Date of Implementation:1996-01-02

standard classification number

Standard ICS number:Environmental Protection, Health Care and Safety >> 13.280 Radiation Protection

Standard Classification Number:Medicine, Health, Labor Protection>>Health>>C57 Radiation Health Protection

associated standards

Publication information

other information

Release date:1996-05-23

Review date:2004-10-14

Drafting unit:Institute of Radiation Medicine, Shanghai Medical University

Focal point unit:Ministry of Health

Publishing department:State Administration of Technical Supervision Ministry of Health of the People's Republic of China

competent authority:Ministry of Health

Introduction to standards:

This standard specifies the radiation health protection requirements for relevant personnel and workplaces in clinical nuclear medicine. This standard applies to units and personnel that use radionuclides and drugs for diagnosis and treatment (excluding plaster therapy) in clinical nuclear medicine. GB 16360-1996 Clinical Nuclear Medicine Radiation Health Protection Standard GB16360-1996 Standard download decompression password: www.bzxz.net

Some standard content:

National Standard of the People's Republic of China
Radiological protection standard for clinical nuclear medicine
Radiological protection standard for clinical nuclear medicine1 Subject content and scope of application
GB16360—1996
This standard specifies the requirements for radiological protection of relevant personnel and workplaces in clinical nuclear medicine. This standard applies to the diagnosis and treatment of clinical nuclear medicine using radionuclides and drugs (excluding units and personnel using dressing treatment).
2 Referenced standards
GB4792—1984 Basic standards for radiological protection GB8703—1988 Radiation protection regulations
WS2—1996 Radiological health requirements for the management of medical radioactive waste3 Classification and zoning of workplaces
3.1 The open workplaces of nuclear medicine are divided into three levels according to the weighted activity of the operating radionuclides, see Table 1. Table 1 Classification of workplaces for clinical nuclear medicine1) Division
Note: 1) According to Publication No. 57 of the International Commission on Radiological Protection (ICRP). 2) Weighted activity = planned daily maximum operational activity X nuclear decay toxicity weighting coefficient Weighted activity 2), MBq
50~50000
Correction coefficient of operational nature
3.2 The toxicity weighting coefficients of radionuclides commonly used in nuclear medicine for calculating weighted activity are shown in Table 2. Table 2 Toxicity weighting coefficients of radionuclides commonly used in nuclear medicine Category
Radionuclide
75Se, 89Sr ,1251, 1311
11C,13N,1$0,18F,5Cr,Ge
99mTc,11n,113mn,1231,2011
$H, mKr,12Xe,13Xe
3.3 The correction coefficients established according to the operational nature of nuclear medicine are shown in Table 3. Approved by the State Bureau of Technical Supervision on May 23, 1996 138
Weight coefficient
Implementation on December 1, 1996
Operation mode and area
Cleaning operation
Scintillation counting and imaging
Diagnosis patient bed area
Dispensing and packaging
Simple radiopharmaceutical preparation
Therapeutic dose patient bed area
Complex radiopharmaceutical preparation
GB16360—1996
Table 3 Correction factors for different operation properties
Correction factor
3.4 ​​The nuclear medicine workplace can be divided into three areas according to management needs, namely, the controlled area, the supervised area and the non-restricted area. 3.4.1 Controlled area
Areas where the radiation dose received by personnel working continuously in a year may exceed three tenths of the annual limit, such as operating rooms for preparing and packaging radioactive drugs, drug administration rooms, bed areas for treating patients, etc. 3.4.2 Supervised area
Areas where the radiation dose received by personnel working continuously in a year generally does not exceed three tenths of the annual limit, such as labeling laboratories using radionuclides, imaging rooms, bed areas for diagnosing patients, storage areas for radionuclides or drugs, storage areas for radioactive waste, etc. 3.4.3 Unrestricted area
Areas where the radiation dose received by personnel working continuously in a year generally does not exceed one tenth of the annual limit, such as staff offices, elevators, corridors, etc.
4 Protection requirements for workplaces
4.1 The protection requirements for indoor surfaces and equipment structures of places such as active laboratories, wards, washing rooms, imaging rooms, etc. according to the classification of workplaces are shown in Table 4.
Table 4 Workplace classification according to requirements for indoor surfaces and equipment of different levels of workplaces
No gaps between floor and wall
Easy to clean and not easy to penetrate
Easy to clean
Easy to clean
Easy to clean
Easy to clean
Fume hood 2)
Note: 1) Based on Publication No. 57 of the International Commission on Radiological Protection (ICRP). 2) Only refers to laboratories.
3) Sewers should be short and large water flow pipes should be marked for maintenance. Indoor ventilation
Exhaust fans should be installed
Good ventilation
General natural ventilation
Special requirements 3)
General requirements
General requirements
Cleaning and decontamination equipment
Only equipment needs to be cleaned
4.2 The wind speed of the fume hood for producing and operating radionuclides or drugs should not be less than 1 m/s under half-open conditions. The exhaust port should be 3m higher than the roof of the building within 50m nearby, and an activated carbon filter or other special filter device should be installed. The exhaust air concentration should not exceed the relevant limit.
5 Protection requirements for storage of radioactive materials
5.1 Storage containers or safes for radioactive materials should be properly shielded. The placement of radioactive materials should be reasonable and orderly, easy to take and put, and the radioactive materials taken and put each time should be limited to the required part. 5.2 The storage room for radioactive materials should be regularly monitored for doses, and irrelevant personnel are not allowed to enter. 5.3 Special containers should be used for storage and transportation of radioactive materials. The containers should not be contaminated when taking out and placing the contents in the containers. The containers should be properly protected during transportation.
GB16360-1996
5.4 Radioactive materials in storage should be registered in a timely manner. The registration content includes the production unit, arrival date, type of nuclide, physical and chemical properties, activity and container surface wiping test results.
6 Protection requirements for the operation of radioactive drugs
6.1 There should be a special place for the operation of radioactive drugs. If the drug administration is not carried out in a special place, appropriate protective measures should be taken. The drug should be shielded before use.
6.2 The syringe used for drug administration should be shielded. If it is difficult to shield, the operation time should be shortened. 6.3 The operation of radioactive drugs should be carried out in a tray lined with absorbent paper, and the staff should wear personal protective equipment. 6.4 The operation of radioactive iodide should be carried out in a fume hood, and the operator should pay attention to thyroid protection. 6.5 Eating, drinking, smoking, and irrelevant work and storage of irrelevant objects are prohibited in the control area and the supervision area. 6.6 The use of radioimmunoassay basins containing radionuclides such as H1, C and 125I for the purpose of in vitro radioimmunoassay can be carried out in a general chemical laboratory without special protection.
6.7 After operation, the staff should wash their hands and monitor the surface contamination before leaving the studio. If the contamination level exceeds the corresponding export limit (see Appendix A (Supplement), decontamination measures should be taken. 6.8 Any object taken out of the control area should be monitored for surface contamination level to ensure that objects exceeding the relevant export limit [see Appendix A (Supplement) are not taken out of the control area. Www.bzxZ.net
7 Radiation monitoring
7.1 Routine personal dose monitoring should be carried out for staff in the control area. Personal dose monitoring should be carried out for staff in the supervision area only when it is necessary to determine whether the workplace is safe and to verify the safety of individual operations. 7.2 Personal dosimeters should be worn on the left chest, and dosimeters for monitoring local doses can be worn on the fingers and wrists when necessary. Dose monitoring should be organized and implemented by a dedicated person.
7.3 Routine monitoring of gas and aerosol activity concentrations should be carried out in operating areas where volatile or radioactive gases are used. 7.4 External exposure levels in the workplace and its surroundings should be monitored when verifying the effectiveness of protective shielding. 7.5 Surface contamination monitoring should be carried out regularly in laboratories, wards, washing rooms, and medication rooms. 7.6 All monitoring results should be recorded, including the location, date, instrument model used, and the name of the monitoring personnel. 8 Radioactive waste treatment
8.1 Radioactive waste treatment should be carried out in accordance with WS2-1996. 8.2 Control areas and supervision areas should be equipped with containers for collecting radioactive waste, and the containers should be marked with radioactive signs. Radioactive waste should be collected separately according to long half-life and short half-life, and properly shielded. 8.3 Liquid or solid radioactive waste should be removed from the workplace in a timely manner. Solid waste such as contaminated needles, syringes, and broken glassware should be stored in leak-proof, relatively strong, and properly shielded containers. 8.41-level workplaces and units with radiopharmaceutical treatment tasks should be equipped with sewage pools to store radioactive sewage until it meets the discharge requirements. Waste raw liquid and highly contaminated radioactive waste liquid should be specially collected and stored. 9 Accident recovery measures
9.1 Emergency measures should be formulated in advance, with clear division of responsibilities, and the implementation of emergency measures should be the responsibility of full-time or part-time protection personnel. Training should be conducted at ordinary times.
9.2 Concise emergency measures guidelines should be displayed in the radioactive operation area, and the person in charge of protection in the area should be designated. 9.3 The work area should be equipped with first aid medicines and equipment. On-site first aid should be determined according to the pollution and danger conditions. 9.4 After emergency measures are taken to make the contamination level of the site meet the requirements, the emergency state can be declared over. 140
10 Protection requirements for clinical nuclear medicine diagnosis
GB16360--1996
10.1 The layout of the diagnostic site should facilitate the work process, such as a radioactive storage room at one end, followed by a medication room, a waiting room, and an examination room. Unrelated personnel should be avoided from passing through.
10.2 The medication room and the examination room should be separated. If medication must be given in the examination room, appropriate protective equipment should be provided. 10.3 The waiting room should be close to the medication room and the examination room, and it is advisable to have a dedicated toilet. 10.4 For subjects who use radionuclides only for diagnostic purposes, no special protective measures are required during surgery. 11 Protection requirements for clinical nuclear medicine treatment 11.1 The area where therapeutic doses of radioactive drugs are used should be designated as a control area. After medication, the area 1.5m from the patient's bed or a single ward should be designated as a temporary control area. There should be a radioactive sign at the entrance of the controlled area. Except for medical staff, no other irrelevant personnel are allowed to enter, and patients should not leave the area at will.
11.2 The dispensing room should be close to the ward to minimize the passage of radioactive drugs and patients who have been treated through the non-restricted area. 11.3 The location of the ward and the thickness of its protective walls, floors and ceilings should be determined according to the form and activity of the radioactive nuclides used. The ward should have a protective fence to keep a sufficient distance from the patient, or use additional shielding. Limit the time that staff work nearby. 11.4 Patients receiving treatment should use a dedicated toilet or a dedicated bathroom and toilet. 11.5 The bedding and personal items of the treated patients should be decontaminated after use, and can only be generally handled after the surface contamination radiation monitoring proves that they are below the derived limit [see Appendix A (Supplement)]. 11.6 Used radioactive drug intracavitary syringes, bandages and dressings should be handled as contaminated objects or radioactive waste. 11.7 For patients who have received 131I treatment, the maximum activity allowed in their bodies at the time of discharge is 1.1×10°Bq. 11.8 For patients who have recently received radioactive drug treatment, surgical treatment should follow the following principles: surgery should be postponed as much as possible until the radioactivity level in the patient's body drops to an acceptable level and no radiation safety protection is required. a.
The surgeon and nursing staff performing the operation should wear a personal dosimeter; c. The operating room should be monitored for radiation and decontaminated after the operation, and other objects such as dressings and covers should also be monitored for radiation. If decontamination is not possible, they can be treated as radioactive waste. 11.9 For patients who have recently used therapeutic doses of radionuclides, the treatment of their bodies after death should follow the following principles: a. No special protection is required for burial, cremation, and preservation of the body when it is below the upper limit of different radionuclides listed in Appendix B (Supplement); b. The body inspection should comply with the principles of surgical treatment in Article 11.8; c. Pathological examination of autopsy samples, if the tissue samples taken have obvious radioactivity, should be conducted after they decay to no significant radioactivity. 141
The derived limits of surface contamination are shown in Table A1.
Surface categories
Controlled area surfaces and equipment surfaces
GB 16360—1996
Appendix A
Derived limits of surface contamination
(Supplement)
Derived limits of various types of surface contamination
Classification of toxicity weight coefficients of nuclides
Surfaces in supervised and unrestricted areas Personal bedding, hospital sheets and other body surfaces
Appendix B
Upper limits of bodies containing radionuclides that can be handled without special protection (Supplement)
1 The upper limits of bodies containing radionuclides that can be handled without special protection are shown in Table B1. B1
Table B1 Upper limit of corpses containing radionuclides that can be handled without special protection Radionuclides
198Au (particles)
18Au (colloid)
Additional notes:
Postmortem preservation
This standard is proposed by the Ministry of Health of the People's Republic of China. This standard is drafted by the Institute of Radiation Medicine of Shanghai Medical University. The main drafter of this standard is Xu Rong.
This standard is interpreted by the Ministry of Health's Industrial Hygiene Laboratory, the technical unit entrusted by the Ministry of Health. 142
Bq· crn-2
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