GB 16358-1996 Standard for radiation health protection for unsealed radioactive sources in oil (gas) field well logging
Some standard content:
National Standard of the People's Republic of China
Radiological protection standards for unsealed radioactive sources logging in oil and gas-field
1 Subject content and scope of application
GB16358-1996
This standard specifies the requirements for radiological protection of unsealed radioactive sources (hereinafter referred to as unsealed sources) in oil (gas) fields. This standard applies to the practice of radioactive tracer logging using unsealed sources in oil (gas) fields. 2 Reference standards
GB4792 USA
Basic standard for radiation health protection
GB5294 Method for monitoring individual dose of radiation workers GB8703 Radiation protection regulations
GB9133 Classification standard for radioactive waste
GB11806 Regulations for safe transportation of radioactive materials GB11930 Regulations for radiation protection of open radioactive materials 3 Terms
3.1 Radioactive tracer logging Radioactive tracer logging is a method of determining the movement state of fluid in the well pipe or between the pores of the formation and its distribution law and the quality parameters of the well engineering by using radioactive tracers injected into the well.
3.2 In-well releaser A device that contains radioactive tracers and can be sent into the well to release them into the well at a fixed point or at a fixed time. 4 Requirements for radiological health protection of laboratories and other facilities 4.1 Laboratories
4.1.1 Classification, grading, site selection and layout of laboratories 4.1.1.1 According to the requirements of GB4792 and GB8703, combined with the equivalent annual usage and maximum equivalent daily operation volume of radionuclides used in oilfield logging, the unsealed source laboratory for oilfield logging belongs to the third category open unit, Class B or Class C workplace. 4.1.1.2 Class B laboratories can be set up in a separate building, or on the first floor or at one end of a general building, but must have separate entrances and exits.
4.1.1.3 Laboratories should be divided into three areas: clean area (including office, rest room, etc.), low activity area (including instrument maintenance room, radioactive measurement room and changing room, shower and radiation dose monitoring room, etc.) and high activity area (including bottle opening and filling room, source storage and waste storage facilities, etc.) according to the operating radioactivity level and the risk level of radioactive contamination. The airflow direction should be from the low activity area to the high activity area. Approved by the State Bureau of Technical Supervision on May 23, 1996 124
Implemented on December 1, 1996 bzxZ.net
4.1.2 Requirements for hygienic protection in laboratories
GB16358—1996
4.1.2.1 The structure of the floor, walls, doors, windows and internal equipment should be simple, with smooth surfaces and no gaps; the floor should be paved with replaceable and easy-to-decontaminate materials, and equipped with floor drains to connect to the general drainage system; the wall surface below 2m above the ground should be painted with acid-resistant and alkali-resistant paint. 4.1.2.2 A fume hood (or work box) must be set up in the bottle opening and filling room, and the cabinet should maintain a negative pressure of 200Pa, and its exhaust system should be equipped with a filter device; the cabinet should be connected to the storage facilities for low-level radioactive waste liquid; the cabinet should also be equipped with protective facilities to shield β and Y external radiation. 4.1.2.3 There should be good ventilation and lighting. The ventilation frequency in Class B laboratories is 4 to 6 times per hour, and the ventilation frequency in Class C laboratories is 3 to 4 times per hour (or natural ventilation). 4.1.2.4 Set up special collection containers or storage facilities for radioactive waste liquid and solid waste. 4.1.2.5 Class B laboratories should have sanitary passage rooms (including changing rooms, showers and radiation dose monitoring facilities, etc.), and Class C laboratories should have facilities for changing rooms, hand washing and radiation dose monitoring, etc. Water supply uses foot pedals or elbow switches. 4.2 Source storage warehouse
4.2.1 The source storage warehouse should be connected to (or adjacent to) the bottle opening and filling room and have a separate entrance and exit. The materials and structures of the walls, doors and windows should have anti-theft and fire prevention functions.
4.2.2 The floor of the source storage warehouse should be smooth and seamless, easy to clean and easy to wash. The source storage warehouse should have sufficient usable area and good ventilation and lighting.
4.2.3 Walls, doors and windows must have sufficient protective thickness, and the public exposure dose equivalent must be ensured to comply with the provisions of GB4792 and GB8703.
4.2.4 A storage pit or pool must be set up in the warehouse. The source pit (pool) should be kept dry, and its top should be at least 10~20cm above the ground. It should be equipped with a protective cover and can be locked. The air kerma rate in the indoor personnel activity area shall not exceed 25μGy·h-\. 4.3 Storage container
4.3.1 All radioactive nuclides and tracers must be placed in tightly sealed containers, and then placed in storage and transportation containers with certain shielding capabilities according to their radiation characteristics. The outer surface of the container should have a label with the tracer production batch number and the name of the radioactive nuclide, chemical form, physical state, activity and calibration date, as well as a clear ionizing radiation hazard warning sign. An instruction manual containing the above content is also attached. 4.3.2 The inner container for radioactive tracers should be tough and have good sealing performance. Containers that are easily damaged and broken should not be used.
4.3.3 Storage and transportation containers should be easy to carry and easy to put in and take out, and must be lockable. In addition to the container number and radionuclide name, activity and calibration date, there must also be a clear ionizing radiation hazard warning sign and the words "Beware of ionizing radiation" and the name of the unit using it. The air kerma rate at 5cm from the outer surface of the protective container shall not exceed 25uGy·h-, and the air kerma rate at 1m shall not exceed 2.5μGy·h1. The radioactive contamination on the outer surface of the storage and transportation container shall not exceed 4×10-1Bqcm-2 for α and 4 Bq* cm-2 for β.
4.3.4 The wall thickness of the storage and transportation container for storing β radionuclides must be greater than the maximum range of β particles in the container material. When the maximum energy of β particles is above 1MeV, attention should be paid to shielding bremsstrahlung. 4.4 Waste liquid and waste storage facilities
4.4.1 The classification of radioactive liquid and solid waste shall be carried out in accordance with the provisions of GB9133. 4.4.2 The discharge of low-level radioactive waste liquid shall be carried out in accordance with the provisions of GB8703. 4.4.3 Radioactive waste barrels shall be set up in the laboratory, and all solid radioactive waste shall be collected in the waste barrels or temporarily stored in storage facilities. The air kerma rate on the surface of the waste barrels and storage facilities shall not exceed 25μGy·h\1. 4.4.4 Waste liquids that cannot be discharged, such as residual radioactive solutions from experiments and high-concentration container washing liquids, shall be collected in special collection containers according to the length of their half-lives. They can be sealed in storage facilities as radioactive waste. 5.1 General requirements
The operation of unsealed sources for logging should comply with the radiation protection principles and requirements in GB11930, with particular attention to the following points: 125
GB16358-1996
a. Under the condition of meeting the technical requirements, select radionuclides with low toxicity, low radiation energy and short half-life, and minimize the activity used and stored;
b. Use remote operation, and try to use mechanical, automatic and closed operation methods; c. Be proficient in operation technology and strive to shorten the operation time; d. Deal with radioactive contamination in time to prevent the spread of contamination e. Minimize the generation of radioactive waste liquid and waste; f. Strengthen safety protection management to prevent the occurrence of radioactive contamination accidents. 5.2 Laboratory Operation Hygiene Protection Requirements
5.2.1 Before operating a radioactive source, you should make adequate preparations, be familiar with the operating procedures, check the name, activity, date of manufacture, total amount, and sub-packaging amount of the radioactive material, check whether the instruments and equipment are normal, whether the ventilation is good, and check whether the actual activity is consistent with the labeled activity. 5.2.2 When adopting new technologies and methods, they should be confirmed to be feasible through "simulation tests", and only after being recognized as proficient in operation by the radiation health protection agency can they be officially operated.
5.2.3 Operations such as opening bottles, sub-packaging, preparing, evaporating, and drying solutions, or when gases or aerosols are generated, must be carried out in a fume hood or operation box. Radioactive operations that are prone to contamination must be carried out on a workbench covered with easily decontaminated materials or in a porcelain plate. 5.2.4 When absorbing radioactive solutions, it is strictly forbidden to absorb by mouth. 5.2.5 The workplace should be wet-cleaned frequently, and cleaning tools must not be mixed with non-radioactive areas. 5.2.6 Radiation workers must understand the principles of handling radioactive contamination accidents and be familiar with the methods of handling radioactive contamination accidents (see Appendix A).
5.3 Health protection requirements in well logging
5.3.1. The release of radioactive tracers during logging should be carried out in the downhole release method. The downhole releaser containing the tracer is sent into the wellbore at a certain depth together with the logging instrument, and the radioactive tracer is released in the wellbore under the control of the wellbore. 5.3.2. When the wellhead release method is adopted, the tracer should be first encapsulated in a container or package that is easy to break or crack in the well, and the method of one-time delivery to the wellhead should be implemented; it is forbidden to use the method of directly pouring the tracer into the wellhead to prevent the pollution of the operation site. 5.3.3. Before releasing the radioactive tracer, it is necessary to carefully check that the gates at the wellhead, the pressure and water flow of the well pipe are normal, the well pipe and casing are unobstructed, and the wellhead plug and the blowout prevention box are tightly structured. Then, the tracer is released according to the normal operating procedures to prevent the well water containing the radioactive tracer from spraying back from the wellhead and polluting the well site and the environment.
5.3.4. When operating the radioactive tracer and supporting the source-carrying downhole releaser or injection tester in and out of the wellhead, an operating tool of appropriate length must be used.
5.3.5 The air kerma rate at the logging site exceeds 2.5μGy·h-1, and the area may be contaminated by radioactivity and should be designated as a warning area. Ionizing radiation hazard warning signs should be set up around it to prevent unauthorized personnel from entering. 5.3.6 On-site logging operators must wear special work clothes, hats, masks, gloves and other personal protective equipment that meet the requirements, and they must be kept and handled in a unified manner. When operating strong radioactive sources, lead protective screens and lead protective glasses should also be used. 5.3.7 Before and after the radioactive tracer logging construction, routine monitoring must be carried out in accordance with 7.3 and 7.4, and abnormalities must be properly handled in a timely manner. 5.3.8 Unused or remaining radioactive tracers (or together with the releaser) and radioactive waste must be brought back to the laboratory for treatment. 5.3.9 After each use, the downhole releaser and the isotope chamber of the isotope injection and measurement instrument must be brought back to the laboratory and rinsed, decontaminated, repaired and maintained in a special washing pool by a dedicated person before use. 6 Health protection requirements for the transportation of unsealed sources for well logging 6.1 When transporting outside the oil field, the packaging and transportation tools should comply with the relevant provisions of GB11806. 6.2 Special (part-time) vehicles for carrying radioactive materials for well logging must be equipped with safety devices and protective facilities for fixed source tanks, and can be interlocked with fixed objects on the vehicle.
The external radiation dose received by the driver should comply with the relevant provisions of GB4792. The air kerma rate on the outer surface of the vehicle shall not exceed 25μGy·h-1, and shall not exceed 2.5μGy·hl at 1m from the outer surface of the vehicle. 126
GB16358-1996
6.3 The tools for carrying or transferring radioactive sources must be flexible, easy to use, reliable in performance, and keep an appropriate distance between the radioactive source and the human body.
7 Protection monitoring
7.1 Personal dose monitoring shall be carried out in accordance with the provisions of GB5294. 7.2 The radiation level and surface radioactive contamination level of all radioactive nuclide containers and their outer packaging, storage and transportation equipment must be measured before and after use.
7.3 Before and after each high-activity operation and on-site logging operation in the laboratory, the radiation level in the workplace and the radioactive surface contamination of equipment and places must be measured. If necessary, the concentration of radioactive aerosols in the air should be measured. 7.4 When the experimental and logging operators leave the laboratory or the site after work, the radioactive contamination level of their exposed skin, work clothes and personal protective equipment must be measured. If contamination is found, it must be handled immediately and properly. 5 Under normal circumstances, the laboratory radiation level and the radioactive contamination level of equipment, ground and wall surfaces are comprehensively monitored once a month. 7.5
S Environmental dose monitoring shall be carried out in accordance with the provisions of GB8703. 7.6
A1 Handling principles
Take decontamination measures as soon as possible;
Prepare appropriate decontamination reagents;
GB16358--1996
Appendix A
Principles and emergency measures for handling radioactive contamination accidents (reference)
Choose reasonable decontamination methods, prevent cross-contamination and expansion of contamination, and properly handle waste and waste liquid;
Wear effective personal protective equipment;
Record the accident process and handling situation in detail, and keep the files properly. A2 Emergency handling measures
General contamination accidents
A2.1.1 Liquid radioactive material spills and leaks can be dried with absorbent balls or absorbent paper. Powdered radioactive material can be removed with adhesive tape or wet rags, and then carefully washed with warm water. To prevent the spread of contamination, the decontamination procedure should start from the lightly contaminated surroundings to the heavily contaminated areas.
A2.1.2 If the effect of repeated cleaning is not obvious, effective decontamination agents can be selected for further decontamination according to the chemical properties of the radionuclides and the properties of the contaminated surface.
A2.2 Serious contamination accidents
A2.2.1 Immediately notify other personnel on the scene, and quickly mark the scope of contamination to prevent other personnel from entering the contaminated area. A2.2.2 When the skin or wound is contaminated, it should be cleaned immediately; when the eyes are contaminated, they should be rinsed with water immediately; if radioactive substances may enter the body, medical personnel should be notified immediately, and emergency measures should be taken in time if necessary. A2.2.3 After taking necessary measures to reduce hazards and prevent the spread of contamination, personnel in the contaminated area should take off contaminated clothes and leave them in the contaminated area and leave the area immediately.
A2.2.4 After the accident occurs, the protection person in charge and the supervisor should be notified as soon as possible, and the relevant supervisory and management departments should be reported immediately. The protection personnel should quickly propose a comprehensive plan to deal with the accident and assist the supervisor in organizing its implementation. After the contaminated area has been decontaminated and monitored, work can resume only with the approval of the protection personnel.
A2.2.5 Record the course of the accident and the handling situation in detail as a basis for finding the cause of the accident, improving protection work, and identifying health conditions. A3 Commonly used decontamination reagents and methods
Commonly used decontamination reagents and methods are shown in Table A1. Table A1 Commonly used decontamination reagents and methods
Surface types
Glassware
And porcelain products
Decontamination reagents
Soap, detergent
Chromic acid mixture, citric acid, hydrochloric acid
Mix with water to scrub and rinse
Operation method
Soak the vessel in 3% hydrochloric acid and 10% citric acid solution for 1 minute h, then take it out and wash it with water, then put it into the washing liquid (i.e. saturated solution of potassium dichromate in concentrated sulfuric acid) for a while, take it out and rinse it with water
Concentrated hydrochloric acid is not suitable for carbon-14,
iodine-131, etc.
Surface types
Clothing
Metals
Paints
(including varnished cloth)
Rubber products
Remove the surface
Decontamination agents
Soap or washing powder
Citric acid, oxalic acid| |tt||Cut and repair
Soap or detergent
GB16358--1996
Continued Table A1
Operation method
Use tools to plane off a few millimeters of the surface
When the pollution is greater than 1000 pulses/min, wash it with a washing machine. If the pollution is less than 1000 pulses/min, it can be washed with ordinary methods
Wash with a washing machine if the pollution level is high
Cut off the contaminated part for waste disposal, and then use a cloth to repair it. Soak and wipe it. Cleaning method
9%~18% hydrochloric acid or 3%~6% sulfuric acid solution
citric acid or dilute nitric acid
heating method
3% ammonium citrate aqueous solution or 10% phosphoric acid
sodium aqueous solution or 10% EDTA solution
10% dilute hydrochloric acid
ammonium citrate
acids or carbon tetrachloride
water, warm water, steam, detergent
3% citric acid or oxalic acid solution
1% sodium phosphate aqueous solution
Organic solvent or concentrated solution of sodium hydroxide or potassium hydroxide
10% dilute hydrochloric acid
Scrape (shear) method
Dilute nitric acid
First wet the surface, then brush it, and finally rinse it with water. Soak the stainless steel in 10% citric acid solution for 1 hour, then rinse it with water, then soak it in dilute nitric acid for 2 hours, and then rinse it with water
Act in heated 10% nitric acid solution for about 15 minutes, then use 10% hot oxalic acid solution or 10% sodium oxychloride solution or 0.5% silicofluoride ammonia nitrogen (NH,SiF. ) solution scrub
Scrub, rinse with water
Scrub·Rinse with water
Dilute with kerosene or other organic solvents and scrub
Scrub with its diluent
Rinse the contaminated area
Gradually dissolve and remove the paint
General cleaning
Wash and rinse
When general decontamination still does not meet the requirements
Nylon is suitable for citric acid,
1Viscose and kapok are suitable for oxalic acid
Applicable to local
Severe pollution
The effect is not good, suitable for
Low pollution||t t||Most metals cannot
have obvious damage to the surface; suitable for stainless steel
good effect
surface damage
the decontamination effect of Yanqi is relatively good, which can reach 50%~90%
cannot be used for paint on lead
cannot be used for varnished cloth
suitable for local pollution
not applicable to carbon-11, iodine-131
additional instructions:
GB16358-1996
This standard is proposed by the Ministry of Health of the People's Republic of China and the Ministry of Energy of the People's Republic of China. This standard is drafted by the Institute of Radiation Medicine of Shandong Academy of Medical Sciences and Shengli Oilfield Health and Epidemic Prevention Station. The main drafters of this standard are Zong Xiyuan, Qiao Dongliang, Deng Taiping, Yang Yingxiao, Sun Zuozhong, Zhang Huazong, and Hu Shiliang. This standard is interpreted by the Ministry of Health's Industrial Hygiene Laboratory, the technical unit entrusted by the Ministry of Health. 130
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