Some standard content:
1 General Rules
National Standard of the People's Republic of China
The rule For radiation protection of particle accelerators
UDC 621.384.6
: 614.898.5
GB 5172-85
1.1 In order to strengthen the management of radiation protection of particle accelerators, protect the environment, and ensure the health and safety of workers and nearby residents, this rule is formulated in accordance with G8-74, "Radiation Protection Rules", with reference to relevant international radiation protection standards, and in combination with the radiation protection status of domestic accelerators.
1.2 This rule applies to particle accelerators (excluding medical accelerators and mobile accelerators such as sealed neutron tubes) with a single nuclear energy of accelerated particles below 100 MeV. 1. All units with particle accelerators must formulate implementation rules in accordance with the requirements of this rule and in combination with the characteristics of the accelerators of the unit.
1.4 In the work of accelerator radiation protection, a balance should be struck between the benefits of reducing the dose and the cost thereof, so that the collective dose equivalent generated during the operation of the facility is kept at the lowest level that can be reasonably achieved, and the dose equivalent received by individuals shall not exceed the dose equivalent limit. 1.5 Units that construct, expand or renovate accelerator facilities must prepare an assessment report on the impact of the facility on environmental quality and submit it to the local Ministry of Environmental Protection1 for approval, otherwise they shall not design and (or) construct it. At the same time, they must also register with the local public security department. 1.6 We must care about the health of people working on accelerators and strengthen health management. Such personnel should enjoy the labor insurance benefits stipulated by the labor protection department and other departments.
1.7 These regulations shall be supervised and implemented by the local radiation protection department1. 2 Dose equivalent limits
2.1 The dose equivalent of occupational radioactive workers who are uniformly irradiated throughout their body or the effective dose equivalent of non-uniformly irradiated throughout their body shall not exceed 50mSv (5rem) per year. For individuals in the public, it shall not exceed 5mSv (0.5rem) per year. 2.2 The dose equivalent of the lens of the eye of occupational radioactive workers shall not exceed 50mSv (5rem) per year, and the dose equivalent of other tissues or organs shall not exceed 500mSv (50ren) per year. For individuals in the public, the dose equivalent of any organ or tissue shall not exceed 50mSy (5rem) per year.
2.3 In the case of external irradiation only, the deep dose equivalent index should be lower than 50mS (5rcm) per year. 2.4 In the case of internal irradiation only, the amount of radioactive material ingested per year should be lower than the ALI listed in Appendix C (Supplement). 2.5 In the case of combined internal and external irradiation, in order to ensure that the annual maximum dose limit is not exceeded, the following two formulas must be satisfied simultaneously: Hd
Wu Zhong:
Hd—annual deep dose equivalent index, Sv (rem)Ht—annual deep dose equivalent limit, Sv (rem)——annual intake of the ith radionuclide, Bq (Ci)National Bureau of Standards issued on May 10, 1985
（2）
Implementation on January 1, 1986
GB 5172-85
（ALI),—annual intake limit of the jth radionuclide, Bq (Ci)His—annual superficial dose equivalent index, Sv (rem)HskL———skin dose limit, 500mSv (50rem). 2.6 When necessary, with the approval of the radiation safety agency, occupational radioactive workers may be allowed to receive radiation exceeding the annual dose equivalent limit. However, the dose or dose equivalent of a single non-event shall not exceed twice the annual limit; the total dose equivalent or dose equivalent of such radiation shall not exceed 5 times the annual limit. Persons of childbearing potential, such as women and persons under the age of 18, shall not receive such radiation. 2.7 Women, lactating women and interns aged 16 to 18 who engage in radioactive work shall work under the condition that the annual radiation does not exceed 3/10 of the annual dose equivalent limit, and the dose equivalent rate is required to be relatively uniform. Persons under the age of 16 are prohibited from engaging in radioactive work. 2.8 The annual average dose equivalent of all radioactive workers working with accelerators shall be less than 5 mSv (0.5 rem). 2.9 The level of radioactive material contamination on the surface shall be lower than the values listed in Appendix D (Supplement). 2.10 The effective dose equivalent of stray radiation, radioactive gases and radioactive wastewater produced by accelerators to individuals in key groups should be less than 0.1 mSv (10 mrem) per year. 3 Design principles for radiation protection facilities
3.1 General requirements
3.1.1 During the planning and design phase of accelerator facilities, full consideration must be given to the contents of radiation protection facilities, including the shelter, required equipment, laboratories and staffing. 3.1.2 The radiation protection facilities of the accelerator must be designed at the same time as the project, implemented and put into operation at the same time. 3.1.3 During the design phase of the accelerator facility, full consideration should be given to the possibility that the accelerator may increase the beam current, increase the energy and expand its application in the future, so appropriate room should be left for radiation protection facilities. 3.1.4 The design of the accelerator facility should be participated by the radiation protection engineer: During the implementation phase, the radiation protection personnel should check the quality of the radiation protection facilities to ensure the design requirements. 3.2 Radiation Shielding
3.2.1 The thickness of the shielding body of the accelerator must be designed according to its possible maximum radiation output based on a comprehensive consideration of the type, energy and beam intensity of the accelerator particles and the target material. 3.2.2 The thickness of the shielding body of the accelerator should also be based on The type of adjacent areas and their populations are determined so that the collective dose of the group is kept as low as reasonably achievable. It must also be ensured that the dose received by individuals does not exceed the corresponding dose exposure limit.
3.2.3 When calculating the shielding thickness, a 2-fold safety factor must be given. 3.3 Radiation safety system
3.8.1 The main control system that determines the radiation generated by the accelerator should be controlled by a switch key. 3.3.2 The doors of the accelerator hall and target hall must be equipped with interlocking devices, and radiation can only be stopped when the doors are closed. 3.3.3 Emergency stop or emergency beam cut-off switches should be installed at locations that are easily accessible to personnel in the accelerator and target hall, and such switches should be marked with warning signs.
3.3.4 Personnel in the accelerator hall and target hall Flashing or rotating red warning lights should be installed in easily visible places. Alarm devices should be installed. Status indicator lights should be installed in corridors, entrances and control consoles leading to the radiation area. 3.3.5 A remote control radiation monitoring system should be installed away from the radiation area and radiation wind. The digital display device of the system should be installed at the control console or monitoring position. When the radiation exceeds the predetermined level, the alarm and (or) light warning device of the system should send a warning signal. 3.3.6 Each accelerator must be equipped with other radiation monitoring devices according to its characteristics, such as personal dosimeters, portable monitors, gas monitors, etc.
3.3.7 The components of the radiation safety system must be of good quality and the installation must be reliable. The components of the system should be resistant to radiation damage. 3.4 Ventilation system
GB 5172-85
3.4,1 To discharge toxic gases (such as ozone) and airborne radioactive substances, ventilation devices must be installed in the accelerator facility. 3.4.2 The exhaust rate of the ventilation system should be determined according to the amount of harmful gases that may be produced and the needs of the operation. The air inlet of the ventilation system should avoid being contaminated by the exhaust gas. 3.4.3 When the ventilation duct passes through the shielding body, measures must be taken to ensure that the shielding effect of the shielding body is not significantly weakened. Radiation safety in operation
4.1 Acceptance of radiation protection facilities
4.1.1 After the accelerator facility is completed, the radiation protection facilities should be accepted, including: radiation screens, interlocking and warning systems, radiation monitoring systems, ventilation systems; laboratories or facilities for radiation protection. After these items meet the design requirements and are issued a license by the local radiation protection management department, the accelerator can be officially put into operation. 4.2 Operation Procedure
4.2.1 All operators of the accelerator must receive basic radiation protection training before work, master the use of the radiation safety system of this machine (including radiation measuring instruments), and can be transferred to the standard operator after passing the assessment. 4.2.2 The machine can only be started when the following conditions are met at the same time: b. The type of accelerated particles, acceleration voltage and preset value are consistent: c. The digital display device on the console can work normally c. The interlocking and warning system can work normally
d. No one is allowed in the accelerator hall and target hall,
e All protective doors of the accelerator hall and target hall are closed. 4.2.3 During the operation of the accelerator, the operator on duty must keep the switch key safe, and the accelerator must be locked when it is not in operation. 4.2.4 The accelerator's start and stop must be operated by the control switch on the console. Except in emergency situations, the accelerator shall not be shut down by cutting off the interlock.
4.2.5 When shutting down by cutting off the interlock or emergency switch, the cut-off position must be manually reset before the accelerator can be restarted by the main control switch on the console.
4.2.6 The interlock system shall not be bypassed without special reasons. When the interlock system needs to be bypassed for the above operation, it must be done as follows: a. Approved by the duty personnel and radiation safety personnel: b. Display on the console and record in the operation log c. Reset as soon as possible:
d. Take other safety measures.
4.3 Operation and storage of radioactive materials.
4.3.1 When operating radioactive materials (such as changing targets, handling activated components, and processing and welding radioactive materials, etc.), it must be carried out in designated places, and the operating rules must be strictly followed. Corresponding radiation monitoring should be done well. If necessary, certain personal protection measures and ventilation measures must be taken.
4.3.2 Radioactive materials must be stored in designated places or special containers, and must be properly shielded and marked with radiation hazards. Radioactive materials must be registered and kept by a designated person. 4..3 Targets must be stored in special containers, which should be placed in a well-ventilated fume hood. Waste vacuum pump oil must be stored in special containers and strictly prevent leakage. These storage places should be well ventilated. If these materials are discarded, they should be treated as radioactive waste. 4.4 Maintenance
4.4.1 Before the accelerator is overhauled, the radiation safety officer must conduct radiation measurement, and propose radiation protection measures to be taken during the maintenance according to the actual situation, and carry out maintenance according to safety regulations. 4.4.2 When overhauling the accelerator's air pump, there must be a suitable working surface, and appropriate personal protection measures and ventilation measures must be taken to strictly control contamination and its spread.
4.4.3 After the maintenance, the body surface and clothes of the personnel participating in the maintenance, the maintenance tools and the ground should be monitored for surface contamination. 4.5 Ventilation
GB 5172—B5
4.5.1 After the accelerator is shut down, before people enter the area with airborne radioactivity, the area should be properly ventilated to make the concentration lower than the derivation air concentration listed in Appendix C. However, under the principle of complying with the principle that the internal and external exposure is lower than the annual effective dose equivalent limit, it is allowed to inhale the concentration of radioactive substances in the air once or more times to exceed the derivation air shielding listed in Appendix C. 4.6 Emergency procedures
4.B.1 According to the actual situation of the accelerator, the emergency procedures required to deal with major accidents (or errors) that may occur should be formulated, including the evacuation of people, determination of personal doses, medical tracking, environmental assessment, etc. 4.7 Reliability test
4.7.1 The radiation safety system must be inspected or maintained regularly, and the time interval shall not exceed 6 months, and the inspection records shall be kept. 5 Radiation Monitoring
5.1 Contents and Requirements of Radiation Monitoring
5.1.1 Personal Dose Monitoring
5.1.1.1 External radiation personal dose monitoring shall be conducted for operators, maintenance personnel and experimenters of accelerators. 5.1.1.2 If it is known or suspected that personnel have inhaled or ingested radionuclides, internal radiation monitoring shall be conducted, such as urine sample analysis or whole body counter measurement.
5.1.2 Regional Monitoring
5.1.2.1 During the final commissioning phase of accelerator facilities and when they are operated to the maximum radiation emissivity state, comprehensive radiation level measurement shall be conducted in the relevant areas with the participation of radiation protection personnel to make an evaluation of radiation safety. 5.1.2.2 If there are changes in the accelerator operating parameters, shielding conditions or the living conditions of the area, which may affect radiation safety, the radiation field shall be re-measured. If necessary, measures shall be taken to ensure that the radiation protection requirements can still be met under the new conditions. 5.1.2.3 After the radiation measurement, the work place shall be classified according to the radiation level, and the following areas shall be taken corresponding measures: a. Supervision area: When working continuously in these areas, the dose received by personnel in one year may exceed 1/10 of the annual dose equivalent limit of occupational radiation workers. Radiation monitoring shall be strengthened in such areas. b. Control: When working continuously in these areas, the dose equivalent received by personnel in one year may exceed 3/10 of the annual dose equivalent limit of occupational radiation workers. In addition to strengthening radiation monitoring, radiation hazard signs shall be set at their entrances or boundaries.
5.1.2.4 During the operation of the accelerator, the radiation level shall be continuously recorded in all areas where the remote monitoring system is installed. When it exceeds the predetermined threshold, the system shall issue a signal of light (or light). Necessary radiation inspections shall be carried out for other areas. 5.1.2.5 When the accelerator is shut down, personnel shall cooperate in radiation monitoring when entering the accelerator hall or target hall. 5.1.3 Surface contamination monitoring
5.1.3.1 Places where radioactive materials (or radioactive materials) are stored and used, as well as areas where radioactive contamination may exist, must be monitored for surface contamination regularly.
5.1.3.2 In areas where radioactive materials may cause surface contamination, the contamination levels of equipment, walls and floors should be monitored regularly.
5.1.3.3 After personnel handle radioactive materials, their body surfaces and clothing should be monitored for surface contamination. 5.1.3.4 When the surface contamination level of various objects exceeds the corresponding limit value, protective measures or timely decontamination should be taken to prevent the spread of contamination.
5.1.4 Airborne radioactivity monitoring
5.1.4.1 The airborne radioactivity concentration in areas where airborne radioactive materials exist should be monitored continuously or regularly. 5.2 Selection of measuring devices
5.2.1 The types and number of radiation monitoring instruments or devices that should be equipped in the accelerator facility mainly depend on the size, complexity and purpose of the accelerator, but any accelerator must be equipped with at least two (types) of measuring instruments for each type of radiation it produces. 5.2.2 The equipped radiation measuring instruments must! Have the following functions:. Have the following accurate specifications for the radiation to be measured
GB6172-85
b. The lower limit of measurement of the instrument is lower than 2.5×10-2mSv-hl (0.25mrem·h2\) c. The instrument has sufficient upper limit of measurement so that it can indicate the radiation level in the monitored area. 5.3 Records of radiation measurements
5.3.1 Records of radiation measurements should be kept, including: a. The time, place and month of measurement
b. Type, energy and beam intensity of accelerated particles, c. Type of target,
Position of collimator and magnet;
Radiation detector used,
f. Results and suggestions,
g. Personnel involved in the measurement.
5.4 Calibration and maintenance of instruments
5.4.1 In order to use the instrument reasonably, its performance and limitations must be well known. Therefore, for each instrument, the following performance information must be given: Response of the instrument to the radiation to be measured,
b. Energy response!
c. Ability to distinguish other types of radiation, d. Response to humidity, temperature and pressure; e. Directional response.
5.4.2 Radiation measuring instruments must be calibrated regularly, with an interval of no more than 1 year. Calibration must also be performed after each maintenance. 5.4.9 For instruments that are frequently used or used continuously, the working performance must be tested once a day or week. 6 Radiation Safety Management
6.1 Radiation Safety Organization and Responsibilities
6.1.1 Any unit with accelerators must establish a radiation safety organization or appoint a full-time (part-time) radiation safety officer according to the number and complexity of the accelerators owned by the unit. 6.1.2 The duties of the radiation safety organization are:
8: According to the requirements of this regulation, cooperate with relevant institutions to formulate implementation rules and supervise their implementation, b. Provide education and training on radiation safety for operating personnel and experimental personnel! c. Report monitoring results to the competent department of the unit regularly, and put forward radiation safety evaluation and improvement suggestions, d. Participate in the investigation and handling of radiation safety accidents e: Check radiation safety facilities, monitor radiation levels, control radiation hazards, and notify operating personnel and experimental personnel of necessary situations: Report major abnormal situations to the competent department of the unit in a timely manner! 1f: Due to radiation safety reasons, the radiation safety personnel have the right to propose to stop the operation of the accelerator. 6.1.3 Qualifications of radiation safety personnel
a: The radiation safety design and evaluation of the accelerator must be participated by radiation protection personnel at the engineer level; b. All radiation cases must be led by radiation protection personnel with a technician title or above; c. The person in charge of the radiation safety organization should be a radiation protection personnel at the engineer level or above. 6.2 Health management
6.2.1 For those who are preparing to work in accelerators, a pre-employment physical examination is required, and only those who meet the health requirements can participate in this work. 6.2.2 For personnel who have been engaged in accelerator work, medical examinations should be carried out regularly, health records should be established, and an assessment should be made based on their health status whether the radioactive work they are engaged in is suitable or should be subject to certain restrictions. 6.2. For personnel who have received emergency or accidental irradiation, reasonable medical follow-up research and certain treatment measures (including labor insurance benefits) should be taken according to the degree of exposure. 6.2.4 For personnel who have been diagnosed with occupational radiation diseases, in addition to providing necessary labor insurance benefits in accordance with relevant regulations, complete medical measures should be taken to enable them to recover as soon as possible.
6.3 Technical Files
GB5172—85
6.3.1 In addition to properly preserving the original radiation protection design files of the accelerator, the following information should also be preserved: : Personal dose records. When personnel are transferred, a copy should be made to transfer to the new job; after the death of a person, except for those who have disputed the cause of death, other personnel can keep it for another 10 years
b. Radiation accident situation report and its handling opinions, radiation protection evaluation report and valuable monitoring results, and background survey data. These data should be kept for a long time;
c. Inspection and calibration records of radiation measuring instruments. The preservation period of these data should be the same as the life of the instrument: d. Records of inspection and modification of radiation interlock circuits. The preservation period of these data is determined by their reference value to the operation of the accelerator, and generally should be the same as the life of the accelerator. 7 Environmental protection and three wastes treatment
7.1 All units with accelerators should do a good job in environmental protection, strive to reduce the amount of radioactive "three wastes" produced, and discharge as little radioactive substances as possible into the environment.
7.2 Units with accelerators should establish corresponding radioactive wastewater and waste storage sites or treatment facilities based on the generation of radioactive "two wastes".
7.3 Radioactive wastes should be classified and treated according to their half-life and whether they can be incinerated. When incinerating radioactive wastes (such as waste vacuum pump oil), there should be a special incineration furnace.
7.4 The discharge of radioactive wastewater (mainly activated cooling water) in accelerator facilities must be strictly controlled. Before discharge, decay measures and purification and filtration measures must be taken, and radiation monitoring must be carried out. 7.5 For accelerators using xenon targets with high xenon content or producing high levels of airborne radioactivity, purification and filtration measures should be taken at the discharge outlet of the fore-stage pump or the ventilation system.
7.6 The environmental hazards of accelerator facilities should be investigated or evaluated once a year, and environmental monitoring and evaluation should be carried out in a timely manner under special circumstances.
GB5172—85
Appendix A
Explanation of Terms
(Supplement)
Except the following terms, other terms used in these regulations can be found in GB4960-85 "Nuclear Science and Technology Terms". A.1 Target
Refers to the material with which the accelerated charged particles interact to produce useful radiation. A.2 High radiation zone
refers to an area accessible to workers, where the radiation level may cause the effective dose equivalent received by the human body to exceed 1mS (100mrem) in any 1 hour.
A, Radiation zone
refers to an area accessible to workers, where the radiation level may cause the effective dose equivalent received by the human body to exceed 5×10-mSv (5mrem) in any 1 hour, or the effective dose equivalent received in any 5 consecutive days to exceed 1mSv (100mrem).
A. Critical resident group
The resident group with the highest level of exposure among all resident groups living and living around the accelerator facility. 6.2.3 For those who have received emergency or accidental exposure, reasonable medical follow-up research and certain treatment measures (including labor insurance benefits) must be carried out according to the degree of exposure. GB5172-B5
Appendix B
Dose estimation
(Supplement)
Daily 1 Dose estimation should consider: absorbed dose and absorbed dose rate, human irradiated parts and range, radiation penetration ability, radiation quality factor Q.
B.2 In radiation protection, dose equivalent is used to determine the dose received by the human body. Dose equivalent H is defined as the product of absorbed dose D, quality factor Q and other correction factors N,
where: H-
-dose equivalent, Sy (rem);
absorbed dose, Gy (rad),
-correction factor, take! ,
quality factor.
The quality factor is a factor that depends on the linear energy transfer density LET. For X-rays, V-rays and electrons, Q is 1. For neutrons, when the energy distribution data are unknown, Q is 10.
B.4 When estimating neutron dose, it is sometimes convenient to use the dose rate (n·cm-2-s-\). Under the condition that the neutron energy spectrum is known, the neutron dose rate can be estimated based on the neutron dose rate conversion factor. For conversion factors and quality factors, see Table B1. Table B1www.bzxz.net
2.5×10-*
1 ×10-
1 ×10-
1 ×10-
1 ×10*1
1 ×10-4
1 ×10*
1 ×10
5 ×101
1 ×102
Conversion factor between injection and dose ×102
n.cm**.s-1/mSv-h-1
Quality factor
B,5 The effective dose equivalent HE (Sv or sv) for whole body exposure is equal to the dose equivalent Hr (Sv or sv) of the irradiated organ or tissue multiplied by the sum of the corresponding weighting factors, that is:
GB 517285
He = WH
The weighting factors of the relative risk of each tissue are shown in Table B2. B,6 When receiving combined internal and external radiation, the total dose equivalent is equal to the sum of the internal and external dose equivalents. Table B2
Tissues or organs Uterus
Red pulp
Thyroid
Bamboo surface
Other tissues"
·Refers to the remaining 5 tissues or organs that receive the highest dose equivalent. The relative risk weight of each is taken as 0.06, and the radiation received by all other remaining tissues can be ignored.
GB 5172—B5
Appendix C
Annual intake limits and derived air concentrations of some radionuclides (supplement)
C.1 The annual intake limits (ALI) and derived air concentrations (D.AC) listed in the table of this appendix are specified for occupational radiation workers.
C.2 The annual intake limits in brackets in the table of this appendix are specified for non-stochastic effects on specific organs or tissues. The organization has marked below the value.
C.9 In Tables C1 to C45, the unit of ALI is Bg and the unit of DAC is Bq'm-3. C.4 The values in the table, except 1aN, 16N and 150, are taken from IAEA Safety Series No. 9 (1982). The values of 16N and 150 are taken from IAF.A Technical Report Series No. 188 (1979). C.5 The relationship between DAC and ALI is as follows
D AC = AL1/2.4 × 103
(aqueous solution)
《Elemental structure》
Properties: The estimation of DAC includes absorption through the skin. Where a is all compounds that are absorbed.
b is all compounds that are commonly present except c. c is the oxide, yttrium and nitraldehyde salt of beryllium. Table C2
2 × 109
3 ×109
3 ×105
3 ×109
8 ×105
2 ×101
7 × 104
3×105
（5）
（Organic labeled compound）
（--ammonia)
（carbon dioxide）
flower: a all chemical substances of the crown.
GB 5172—85
2×1010
2×[010
6 ×10b
4×1glo
2×107
2 ×1010
1×107
immersion external irradiation (semi-infinite cloud)
7 ×104
2 ×101
jun no external irradiation (semi-infinite cloud)
2 ×109
(2 × 10°)
3 ×104
byfl. Ll,Na,K.Rb, Cs, Fr. Be. Mg.Ca, Sr, Ba, Ra, Al, Gu, In,Tl,As, Sb, Bt.Fe, Ru, Os, Co, Rh. [r, Ni, P'd, Pt, Cu, Ag. Au.Zn, Cd, Hg. Se, Y, Ti. Zr.Hf,Nh, Ta, Mn, Te, Re and other ferrogen and ferrogen compounds. Nucleus
Note: a, b are all compounds of sodium.
Note: a is all compounds of caesium.
b is all compounds of magnesium except c.
GB 5172-85
2×107
1×10g
c is the oxide, hydroxide, carbide, halide and nitrate of magnesium. Table c9
Note: and all compounds of nitrogen.
6 ×1g6
(9 × 10\)
× L0
(1 ×10')
h is the compounds of H, Li, Na, Rb, Cs, Fr and other elements. b
6 ×107
3×104
2 ×10#
6 ×105
B×10m
2 ×107
1 ×104
2 ×10
8 ×10+
5×1g7
2×104
2×109
7×105
9 × 105
r is the system Jt element, He, Mg, Ca.Sr.Ha, Ra, Al.Ga,In.,TI,Ge. Sn, Pb, As, Sb, Si, Fe. Ru, Os, Co.
Tip: This standard content only shows part of the intercepted content of the complete standard. If you need the complete standard, please go to the top to download the complete standard document for free.