GBZ118-2020 English PDFUS$319.00 · In stock
Delivery: <= 3 days. True-PDF full-copy in English will be manually translated and delivered via email. GBZ118-2020: (Radiation protection requirements for logging in oil and gas fields) Status: Valid GBZ118: Historical versions
Basic dataStandard ID: GBZ 118-2020 (GBZ118-2020)Description (Translated English): (Radiation protection requirements for logging in oil and gas fields) Sector / Industry: National Standard Classification of Chinese Standard: C57 Classification of International Standard: 13.100 Word Count Estimation: 14,136 Date of Issue: 2020 Date of Implementation: 2020-10-01 Issuing agency(ies): State Administration for Market Regulation, China National Standardization Administration GBZ118-2020: (Radiation protection requirements for logging in oil and gas fields)---This is a DRAFT version for illustration, not a final translation. Full copy of true-PDF in English version (including equations, symbols, images, flow-chart, tables, and figures etc.) will be manually/carefully translated upon your order.(Radiation protection requirements for logging in oil and gas fields) ICS 13.100 C 57 GBZ National Occupational Health Standards of the People's Republic of China Replace GBZ 118-2002, GBZ 142-2002 Radiation protection requirements for logging in oil and gas fields 2020-04-03 released 2020-10-01 implementation Issued by the National Health Commission of the People's Republic of China Table of contentsForeword...II 1 Scope...1 2 Normative references...1 3 Terms and definitions...1 4 General requirements...2 5 Radiological protection requirements for storage, transportation and logging sites...3 6 Radioactive waste disposal requirements...5 7 Radiation protection testing requirements for oil and gas field logging...6 Appendix A (informative appendix) Principles and emergency measures for handling radioactive contamination accidents...8 Appendix B (informative appendix) Surface contamination and leak detection methods of radioactive sources...10 References...11Foreword6.6 and 7.1.3 of this standard are recommended clauses, and the rest are mandatory clauses. This standard is formulated in accordance with the "Law of the People's Republic of China on Occupational Disease Prevention and Control" This standard was drafted in accordance with the rules given in GB/T 1.1-2009. This standard replaces GBZ 118-2002 "Oil (gas) field unsealed radioactive source logging health protection standards" and GBZ 142-2002 "oil (Gas) Field Logging Use Sealed Radioactive Source Sanitary Protection Standard." Compared with the above two standards, the main technical changes except for editorial changes are as follows. --- Increase the radiation protection requirements for neutron generator logging (see 5.1.12, 5.1.13 and 5.2.11); -Modified normative reference documents (see Chapter 2, Chapter 2 of GBZ 118-2002, Chapter 2 of GBZ 142-2002); - Deleted the requirement that "all radioactive sources and waste sources used for logging must be stored in the source pit, and frequently used radioactive sources should be one source and one pit" Seek (see 3.3.2 of GBZ 142-2002); --- Modify the requirements of the source storage pit (pool) in the source library (see 5.1.3, GBZ 142-2002, 3.3.2); --Modify sealed sources and unsealed sources to radioactive sources and unsealed radioactive materials (see Chapter 3 to Chapter 7, Appendix A and Appendix B, Chapter 4 to Chapter 5 of GBZ 118-2002 and Chapter 3 to Chapter 4 of GBZ 142-2002); --Revised the control value index of the external radiation leakage in the radiation protection requirements from the air kerma rate to the surrounding dose equivalent rate (see Section 5 Chapter ~ Chapter 7, GBZ 118-2002 Chapter 4 ~ Chapter 6 and GBZ 142-2002 Chapter 3 ~ Chapter 5); --- Delete the conversion coefficient of single energy neutron fluence and effective dose in Appendix B of GBZ 142-2002 (see GBZ 142-2002 Appendix B). Drafting organizations of this standard. Institute of Radiation Medicine, Shandong Academy of Medical Sciences, Sinopec Shengli Petroleum Engineering Co., Ltd. Logging Company, He Southern Institute of Occupational Disease Control. The main drafters of this standard. Deng Daping, Song Gang, Shen Yingjie, Wang Yunfei, Zhang Qinfu, Cheng Xiaojun, Lu Feng, Wang Jingping, Chen Yingmin, Chen Rui, Gao Zeyu, Niu Fei. This standard replaces GBZ 118-2002 and GBZ 142-2002. The previous releases of GBZ 118-2002 are as follows. --GB 16358-1996. The previous releases of GBZ 142-2002 are as follows. --GB 8922-1988. Radiation protection requirements for logging in oil and gas fields1 ScopeThis standard specifies the radiological protection requirements and testing requirements for using radioactive sources, unsealed radioactive materials and neutron generators for logging in oil and gas fields. This standard is applicable to the radiological protection and detection of oil and gas field logging practices using radioactive sources, unsealed radioactive materials and neutron generators.2 Normative referencesThe following documents are indispensable for the application of this document. For dated reference documents, only the dated version applies to this document. For undated references, the latest version (including all amendments) applies to this document. GB 2894 safety signs and guidelines for their use GB 4075 General requirements and classification of sealed radioactive sources GB 11806 Regulations for the safe transportation of radioactive materials GB 11930 Radiation protection regulations for operating unsealed sources GB 14500 Radioactive Waste Management Regulations GB 18871 Basic standard for ionizing radiation protection and radiation source safety GBZ 128 Specification for personal monitoring of occupational external exposure SY/T 5419 Petroleum logging neutron generator and neutron tube technical conditions3 Terms and definitionsThe following terms only apply to this document. 3.1 Capsule Protective shell to prevent leakage of radioactive materials. 3.2 Radioactive source Radioactive material that is permanently sealed in a container or has a tightly-coated and solid state. 3.3 Unsealed radioactive material Radioactive material that is not permanently sealed in the envelope or tightly consolidated in the covering. 3.4 Neutron tube The ion source, acceleration system, target and air pressure adjustment system are sealed in a glass, ceramic, stainless steel, etc. tube to form a structure Compact vacuum device. 3.5 Neutron generator for well logging It consists of a neutron tube and an external circuit of the neutron tube. The external circuit of the neutron tube is usually composed of an ion source circuit and a sealed acceleration high voltage. 3.6 Radioactive tracer logging Use the unsealed radioactive material injected into the oil well as a tracer to determine the movement state and distribution of the fluid in the well pipe or between formation pores Laws and methods of wellbore engineering quality parameters. 3.7 In-well releaser A device that contains radioactive tracers and can be sent downhole to release them into the well at a fixed point or time.4 General requirements4.1 The radioactive source should meet the requirements of GB 4075 for oil and gas field logging radioactive sources to ensure reliable sealing performance. Radioactive source should have radioactive source code Number and the name or symbol of the radioactive source nuclide (including the neutron source target nuclide). There should be a description of the radioactive source, and its content should at least include. Number, nuclide name, activity, radiation type, radiation output rate (or fluence rate) of the radiation used and its measurement date, surface contamination and Leak detection result and detection date, etc. 4.2 The operation of unsealed radioactive materials used for logging should comply with the relevant radiation protection principles and requirements in GB 11930.Pay particular attention to the following A few points. a) Under the conditions of meeting the logging technical requirements, select radionuclides with lower toxicity, lower gamma radiation energy and shorter half-life. And minimize the activity of use and storage; b) Use remote operation, try to choose mechanical, automatic and airtight operation; c) Proficient in operation technology, and strive to shorten the operation time; d) Treat radioactive pollution in time to prevent the spread of pollution; e) Minimize the generation of liquid, solid and other radioactive waste; f) Strengthen safety protection management to prevent radioactive pollution accidents; g) According to the requirements of GB 18871, according to the daily equivalent maximum operating volume of radionuclides used in oil and gas field logging, Hierarchical management shall be carried out in the logging workplaces of radioactive materials. 4.3 When adopting new technologies and methods, “simulation tests” should be used to confirm that they are feasible, and the operation should be confirmed by relevant experts organized by the user unit. After the procedures are made, the formal operation can be carried out. 4.4 Units conducting radioactive logging in oil and gas fields shall be based on the types of radioactive sources, unsealed radioactive materials and logging neutron generators used. Don’t be equipped with external radiation protection testing equipment, radioactive contamination testing equipment and other self-checking equipment, and wear corresponding types for radiation workers Personal protective equipment such as personal dose alarms. 5 Radiation protection requirements for storage, transportation and logging sites 5.1 Radiological protection requirements for storage and radioactive laboratories 5.1.1 Tanks (barrels) (hereinafter referred to as source tanks) that store or carry radioactive sources and unsealed radioactive materials (hereinafter referred to as source tanks) should be easy to transport and take out radioactive sources. It should be single source and single tank and lockable; the outer surface of the source tank should be marked with radioactive source code, nuclide type, factory activity and factory time. It should be signed and printed with a striking ionizing radiation sign and the name of the user unit in accordance with the provisions of GB 2894.Store radioactivity that releases beta rays The wall thickness of the storage and transportation container for nuclides should be greater than the maximum range of the β-ray in the container material. When the maximum energy of the β-ray is above 1 MeV, Bremsstrahlung radiation shielding measures should be taken. 5.1.2 The radioactive material storage warehouse (hereinafter referred to as the source warehouse) should be an independent building, surrounded by walls, and there should be no non-radioactive materials inside the walls. Workers live, work, and place flammable, explosive and other dangerous items. The source bank should have ionizing radiation warning signs and Chinese Description. There should be good lighting and ventilation in the source storehouse, and there should be enough area for use. Eating, drinking, smoking, etc. should not be in the source storehouse. Store For neutron sources larger than 185 GB q (5 Ci) or source libraries for gamma sources larger than 18.5 GB q (0.5 Ci), mechanical lifting and transmission equipment should be provided. The surrounding dose equivalent rate at 30 cm outside the shielding body of the source library, doors and windows, and roofs should not exceed 2.5 μSv/h. 5.1.3 Source storage pits (pools) or storage tanks should be set up in the source reservoir, neutron sources with an activity greater than 185 GB q and γ with an activity greater than 18.5 GB q All sources should be stored in the source storage pit (pool). The depth of the source storage pit (pool) is not less than 100 cm, and it is covered with a protective cover of appropriate material and thickness. The storage source box should be equipped with a corresponding shield according to the type of radioactive source stored and the designed maximum storage activity. Source storage pit (pool) and the appearance of the source tank The surface should be provided with labels indicating the source code, type of nuclide, factory activity, factory time, and storage and retrieval records of the stored radioactive source. 5.1.4 All tracers should be contained in tightly sealed containers (referring to containers directly containing unsealed radioactive substances, hereinafter referred to as inner containers) And then put it into a storage and transportation container with a certain shielding ability according to its radiation characteristics. The inner container and the Sealed radioactive source downhole releasers should be accompanied by production batch number and radionuclide name, chemical form, physical state, activity and calibration date. Sign the label with the eye-catching ionizing radiation sign, and attach the instructions containing the above content. The inner container of the radioactive tracer should be of texture A container that is tough and not easy to be damaged or broken, and has good sealing performance. A striking ionizing radiation sign should be set on the surface of the releaser. 5.1.5 The source warehouse shall establish a management system for the entry and exit of radioactive sources and unsealed radioactive materials, which shall be kept by a dedicated person, with double locks for two persons, and an account, Entry and exit records, regular inventory, and source tank entry and exit should be tested with instruments to confirm whether there are radioactive sources in the source tank and record. 5.1.6 The non-sealed radioactive material laboratory should be set up at the lowest level or one end of a separate building or a general building, with separate access mouth. Special collection containers or storage facilities for radioactive waste liquid and solid waste should be set up. 5.1.7 The laboratory for unsealed radioactive materials shall be divided into clean areas (including the Including offices, restrooms, etc.), low activity areas (including instrument maintenance rooms, radioactivity measurement rooms and dressing, showers and radiation dose testing rooms, etc.) And high activity area (including bottle opening and filling room, storage source warehouse and waste storage facilities, etc.) three areas, low activity area and high activity area are control areas, The clean area is a supervision area, and the control area and the supervision area shall be managed separately in accordance with the requirements of GB 18871.The direction of air flow should be from low activity area to high activity After passing through the filter device, it will be discharged from the dedicated exhaust duct. The outlet of the exhaust duct should be higher than the top floor of the building. 5.1.8 The structure of the floor, walls, doors and windows and internal equipment of the non-sealed radioactive material laboratory should be simple, and the surface should be smooth and seamless. The ground and adjacent walls should be connected in a smooth manner rather than a right angle; the ground should be covered with replaceable and easily decontaminated materials, and a ground leakage should be set to connect radioactive waste. Water treatment system; the wall should be acid and alkali resistant and easy to clean. Class B laboratories should have sanitary passing rooms (including changing clothes, showers and radiation dose testing Facilities, etc.), Class C laboratories should be equipped with facilities for changing clothes, washing hands, and radiation dose testing. Water supply should use foot pedal, elbow or non-contact Inductive switch. 5.1.9 The unsealed radioactive material storage source should be connected to (or adjacent to) the opening and filling chamber and have separate entrances and exits. Walls, doors and windows The material and structure must have the effect of preventing theft and fire. Source pit (pool) for storing unsealed radioactive material and unsealed radioactive material storage source room The ground should be kept dry, smooth and seamless. The ground and adjacent walls should be connected in a smooth rather than right-angled connection, which is easy to decontaminate and wash. 5.1.10 Before operating unsealed radioactive materials, you should make adequate preparations, be familiar with the operating procedures, and check the name and delivery of the radioactive materials. Date, total activity, sub-packing activity, check whether the equipment is normal, whether the ventilation is good, and check whether the actual activity is consistent with the marked activity. When sucking the radioactive solution, a suction ball or siphon device should be used, and it is strictly prohibited to suck it by mouth. The workplace should be cleaned frequently and the cleaning tools should not Mixed with non-radioactive area cleaning tools. 5.1.11 The operations of opening, dispensing, preparing, evaporating, drying the solution or generating gas or aerosol should be carried out in a fume hood, which is easy to manufacture. Contaminated radioactive operations should be carried out on a workbench with easily decontaminated materials or in an enamel tray. Negative pressure should be maintained in the fume hood. When the port is half open, the wind speed at the operation port should be greater than 1 m/s, and the exhaust system should be equipped with a filter; the bottom of the fume hood should be equipped with low-level radioactive waste Storage facilities. 5.1.12 The neutron tube storage should be a separate room, which should be an independent building or one end of the ground floor of a building, and an anti-theft device should be installed. In storage Do not live, work or place other dangerous items such as flammable and explosive. The environmental conditions such as temperature and humidity of the neutron tube storage place should conform to SY/T 5419.Avoid collision and friction during neutron tube transfer. 5.1.13 The test and calibration of the neutron tube should be carried out in a dedicated shielding body. The shielding medium can be concrete larger than 100 cm or larger than For a water layer of.200 cm, special underground test wells can also be used, and the depth of the test well should be greater than 10 m. When there is no special shield, the distance measurement The test neutron tube is not less than 30 m and the range is set as the control area, and the boundary of the control area should be set with a cordon or guard fence, and an ionizing radiation warning should be set Sign, set up a special guard. 5.1.14 When the radioactive source tank for logging uses the source, the surrounding dose equivalent rate caused by transmission at a distance of 5 cm from the surface of the radioactive source tank should not be greater than the control value in Table 1. 5.1.15 The surrounding dose equivalent rate at a distance of 5 cm from the outer surface of the non-sealed radioactive material protective container shall not exceed 25 μSv/h, at a distance of 100 cm The surrounding dose equivalent rate should not exceed 2.5 μSv/h. The outer surface of unsealed radioactive material storage and transportation container and the source of unsealed radioactive material For the radioactive contamination of the ground and countertops in the warehouse, the alpha radioactive material should not exceed 0.4 Bq/cm2, and the beta radioactive material should not exceed 4 Bq/cm2. 5.1.16 The surrounding agent at 30 cm on the surface of the protective cover (or the surface of the source box) of the radioactive source and the unsealed radioactive material storage pit (pool) in the source library The equivalent rate should not exceed 100 μSv/h. The surrounding dose equivalent rate at 30 cm of the surface of the dirt barrel and radioactive waste storage facility should not exceed 25μSv/h. 5.2 Radiation protection requirements for transportation and logging sites 5.2.1 When the radionuclide is transported externally, its radioactive packaging and transportation tools should meet the requirements of GB 11806.The source truck should be equipped with Vehicle radiation detection equipment and vehicle-mounted records. The vehicle-mounted records should contain the code of the transported radioactive source, the type of nuc......Tips & Frequently Asked Questions:Question 1: How long will the true-PDF of GBZ118-2020_English be delivered?Answer: Upon your order, we will start to translate GBZ118-2020_English as soon as possible, and keep you informed of the progress. The lead time is typically 1 ~ 3 working days. The lengthier the document the longer the lead time.Question 2: Can I share the purchased PDF of GBZ118-2020_English with my colleagues?Answer: Yes. The purchased PDF of GBZ118-2020_English will be deemed to be sold to your employer/organization who actually pays for it, including your colleagues and your employer's intranet.Question 3: Does the price include tax/VAT?Answer: Yes. Our tax invoice, downloaded/delivered in 9 seconds, includes all tax/VAT and complies with 100+ countries' tax regulations (tax exempted in 100+ countries) -- See Avoidance of Double Taxation Agreements (DTAs): List of DTAs signed between Singapore and 100+ countriesQuestion 4: Do you accept my currency other than USD?Answer: Yes. If you need your currency to be printed on the invoice, please write an email to Sales@ChineseStandard.net. In 2 working-hours, we will create a special link for you to pay in any currencies. Otherwise, follow the normal steps: Add to Cart -- Checkout -- Select your currency to pay.Question 5: Should I purchase the latest version GBZ118-2020?Answer: Yes. Unless special scenarios such as technical constraints or academic study, you should always prioritize to purchase the latest version GBZ118-2020 even if the enforcement date is in future. Complying with the latest version means that, by default, it also complies with all the earlier versions, technically. |