GB 10252-2009 English PDFUS$419.00 · In stock
Delivery: <= 3 days. True-PDF full-copy in English will be manually translated and delivered via email. GB 10252-2009: Regulations for radiation protection and safety of gamma irradiation facilities Status: Valid GB 10252: Historical versions
Basic dataStandard ID: GB 10252-2009 (GB10252-2009)Description (Translated English): Regulations for radiation protection and safety of gamma irradiation facilities Sector / Industry: National Standard Classification of Chinese Standard: F51 Classification of International Standard: 13.280 Word Count Estimation: 18,148 Date of Issue: 2009-06-19 Date of Implementation: 2010-06-01 Older Standard (superseded by this standard): GB 10252-1996 Quoted Standard: GB 3095; GB 17568; GB 18871-2002; HJ/T 2.2-1993 Regulation (derived from): Announcement of Newly Approved National Standards No. 9, 2009 (No. 149 overall) Issuing agency(ies): General Administration of Quality Supervision, Inspection and Quarantine of the People's Republic of China, Standardization Administration of the People's Republic of China Summary: This Chinese standard specifies the use of Class I radioactive sources �� irradiation radiation and pollution control division of the radiation in the workplace, radiation protection and safety design, environmental assessment irradiation, radiation safety management, radiation safety testing, irradiation equipment decommissioning and emergency requirements. This standard applies to Class I radioactive sources using �� irradiation facility siting, design, construction, operation and decommissioning of radiation protection and safety. GB 10252-2009: Regulations for radiation protection and safety of gamma irradiation facilities---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.Regulations for radiation protection and safety of gamma irradiation facilities ICS 13.280 F51 National Standards of People's Republic of China Replacing GB 10252-1996 Radiation protection and safety norms γ Irradiation Facilities Posted 2009-06-19 2010-06-01 implementation Administration of Quality Supervision, Inspection and Quarantine of People's Republic of China Standardization Administration of China released Table of ContentsPreface Ⅰ 1 Scope 1 2 Normative references 1 3 Terms and definitions 4 radiation and pollution control 2 5 2 division of radiation in the workplace 6 Radiation Protection and Safety Design 2 Environmental Assessment irradiation apparatus 3 7 8 Radiation Safety Management 3 9 Radiation Safety Inspection 4 Managed 10 radioactive sources 5 11 irradiator retired 5 12 6 Emergency Appendix A (informative) irradiation chamber shielding and protection design calculation 7 Appendix B (normative) concentration limits of harmful gases and monitoring 12 Produce Annex C (informative) harmful gases and diffusion calculation 13ForewordAll the technical contents of this standard is mandatory. This standard replaces GB 10252-1996 "radiation protection and safety standards cobalt-60 irradiation facilities." This standard compared with GB 10252-1996, the main changes are as follows. --- By the name of the standard "cobalt-60 radiation protection and safety standards irradiation apparatus" with "radiation protection and safety γ Irradiation Facilities specification"; --- "Scope" to add a chapter include some content, expanding the scope of application; --- "Normative references" All has been modified; --- Added "Terms and Definitions" chapter; --- "Radiation and Pollution Control" made some changes; --- Remove the original "division and workplace requirements" chapter, "non-restricted zone" a; --- Increased "radiation protection and safety," a chapter; --- Increased "environmental assessment irradiation apparatus" chapter; --- Original "radiation protection and safety management" with "Radiation Safety Management"; --- Remove the original "technical requirements for radiation protection and safety" and "security analysis irradiation apparatus" two chapters; --- Original "inventory and inventory of radiation sources" to "Management of Radioactive Sources"; --- The original "Radiation protection and safety testing content" and "radiation monitoring" Merge to "detect radiation safety"; --- Added "retired irradiation apparatus" chapter; --- Original "accident and emergency radiation protection" to "emergency"; --- Added Appendix A and Appendix C, recommended mathematical models for calculating radiation protection and harmful gases. This standard is GB 17568 "γ irradiation device is designed and constructed using standard" support standards. Appendix B of this standard is a normative appendix, Appendix A, Appendix C are informative appendices. The standard proposed by China National Nuclear Corporation. This standard by the National Standardization Technical Committee of nuclear energy. This standard was drafted. Beijing three strong nuclear radiation Engineering Technology Co., MEP Nuclear and Radiation Safety Center, Beijing radio Line Applied Research Center. The main drafters of this standard. Wang Chuan Zhen, Zhou Qifu, Liuyi Gang, Liuqiu Rong Fan deep roots, Jang Hyuk coral, Chen Jian, Peng Wei, Fu Jie. This standard was first released in December 1988, in December 1996 the first amendment, this is the second revision. Radiation protection and safety norms γ Irradiation Facilities1 ScopeThis standard specifies the use of γ irradiation apparatus Ⅰ class sources of radiation and pollution control division, radiation protection and radiation in the workplace Environmental evaluation of safety design, the irradiation apparatus and the radiation safety management, radiation safety testing, irradiation facilities decommissioning and emergency requirements. This standard applies to the use of the site class Ⅰ γ irradiation apparatus radioactive sources, design, construction, operation and decommissioning of radiation protection and safety.2 Normative referencesThe following documents contain provisions which, through reference in this standard and become the standard terms. For dated references, subsequent Amendments (not including errata content) or revisions do not apply to this standard, however, encourage the parties to the agreement are based on research Whether the latest versions of these documents. For undated reference documents, the latest versions apply to this standard. GB 3095 Ambient Air Quality Standard GB 17568 γ irradiation facilities design and construction specifications and use GB 18871-2002 ionizing radiation protection and safety of radiation sources basic standards (IAEA Safety Series, NEQ) HJ/T 2.2-1993 Environmental Impact Assessment Technology Guidelines3 Terms and DefinitionsGB 17568 and established in the following terms and definitions apply to this standard. 3.1 Within the irradiation facility enclosed by a radiation-shielding material with, radiation processing and in working condition due to safety measures for personnel can not enter the interlock Space. 3.2 Penetrating power strong radiation in matter, generally refers to γ radiation, X-radiation and neutron radiation. This standard refers specifically to shield the irradiation chamber wall table Surface water surface, the roof and a reservoir wells transmission out of γ radiation. 3.3 Important safety control system irradiation apparatus, wherein the operation of such components are interrelated, each action parts are subject to pre-regulation Given state and (or) controlled conditions, so long as either a component of any state and (or) does not meet the pre-conditions for the provisions of irradiation can be prevented Sources from the storage device state put into use, or to have been put into use radioactive sources or are immediately returned to the storage state, or resistance Personnel from entering the irradiation device is irradiated from the irradiation chamber to make it. 3.4 The source or the use of a particular practice is possible to predict and estimate the impact on the environment carried out, including the size of the source or practice with special Of the overview of the status of the site or workplace environment analysis and environmental impact under normal, abnormal and may cause accidents or consequences Analysis. 3.5 Environmental protection department under the State Council issued on the basis of the safety review, together with its holder to comply with the specific requirements and conditions Radiation safety license. 3.6 Reached the end of life of the radionuclide or find a leak or licensees are no longer expected to use radioactive sources specified by the manufacturer.4 radiation and pollution control4.1 Individual Dose Control 4.1.1 radiation workers occupational and public exposure dose limits should be in accordance with the requirements of GB 18871-2002. 4.1.2 irradiator engineering design, operation and decommissioning, radiation protection dose constraint value is defined as. a) Radiation Workers' Individual annual effective dose values 5mSv; b) members of the public individual annual effective dose values 0.1mSv. 4.2 Radioactive pollution control 4.2.1 radioactivity concentrations in well water reservoir 60Co source should be controlled 10Bq/L or less. 4.2.2 source storage wells emissions shall meet the following requirements. a) Monthly discharged into the sewer 60Co total activity should not exceed 1 × 106Bq; b) 60Co total activity every emissions should not exceed 1 × 105Bq, and after each discharge with no less than three times the amount of water discharged rinse; c) discharge only after the approval of the regulatory authorities. 4.2.3 in accordance with GB 18871-2002 Table B. 11, staff clothing, surface and workplace equipment, tools, floors and other surfaces β Control the level of radioactive contaminants in Table 1. Table 1 Surface β radioactive pollution level Substances Control unit becquerels per square centimeter Surface type β radioactivity Tables, equipment, walls, floors, Control area 4 × 10 Supervised area 4 Overalls, gloves, work shoes Control area Supervised area Hands, skin, underwear, socks, work 4 × 10-1 When Equipment & Supplies 4.2.4 in the workplace, after decontamination, pollution levels below 0.8Bq/cm2, with a measurement mechanism by qualified and After regulatory permission to make use of ordinary objects, but does not apply to cookware. Divided by 5 radiation in the workplace 6.4 in accordance with the provisions of GB 18871-2002, radiation irradiation device into place. a) control area. irradiation chamber and fan Road; b) supervised area. cargo handling area between the irradiation chamber roof control room, ventilation, equipment room, treatment rooms and other areas.6 Radiation Protection and Safety Design6.1 shield 6.1.1 shield should be designed to ensure the irradiation chamber radiation shielding integrity and security. For weak radiation shielding parts (such as ventilation and wear Wall tunnels, etc.), compensatory measures should prevent leakage beam; irradiation chamber should be designed taking into account the thickness of the roof penetrating radiation and sky diffuse; fan channel design Fans should be crossing the external radiation dose of radiation workers to meet the requirements of 4.1.2; at the maximum design loading source volume, the outer surface of the shield dose levels It shall also meet the requirements of 4.1.2. 6.1.2 source storage wells (including auxiliary shaft) should be designed to ensure that a reservoir wells radiation shielding integrity and security. Wells and well equipment cladding It should be used in good corrosion resistance of stainless steel and ensure good sealing performance and a certain load-bearing capacity; the bottom of the pond should have penetrations (such as Pipes, plugs). Any penetrations through the wall of the pool should be below the normal water level of not less than 30cm. At the maximum design loaded source activity, well above the dose levels should meet the requirements of 4.1.2. 6.1.3 shielding design and computing model calculation parameters refer to Appendix A. 6.2 Irradiation Facility Security System 6.2.1 irradiator design safety systems should follow the principle of defense in depth, and to meet the requirements of GB 17568. 6.2.2 Security facilities should ensure that. --- All safety facilities is active, normal state; --- Or source before mistakenly left unattended in the irradiation chamber, able to help themselves stay as erroneous; --- Security sources when not in place, people can not enter the irradiation chamber; --- A reservoir wells water level indication and alarm when the water level dropped to a critical level security and timely replenishment; --- Safe and effective water treatment system, water quality meet the requirements; --- Staff can not fall into the well; --- Having sufficient mechanical protection of radioactive sources, to avoid collision. 6.3 of harmful gases 6.3.1 radiation concentration generated by the decomposition of ozone and other harmful gases does not exceed the allowable value, the control and monitoring requirements concentration Mitsuke Record B. 6.3.2 ozone generation and emission calculation model and its parameters, see Appendix C. Environmental Assessment 7 irradiation apparatus 7.1 owners prior to construction γ irradiation apparatus shall prepare an environmental impact assessment documents include radiation safety content analysis, and in accordance with national Prescribed procedures for approval. 7.2 Radiation safety analysis should include analysis of normal conditions and accident conditions.8 Radiation Safety Management8.1 Regulated irradiator Location 8.1.1 irradiator, design, construction, operation and decommissioning shall be in accordance with relevant regulations, to regulatory authorities apply approved Or after approval before implementation. 8.1.2 source irradiator design maximum loading capacity increases or facilities involved in radiation safety devices have changed owners regulatory authorities should lodge a Please, after their radiation protection and safety certification before implementation. 8.2 Radiation safety responsibilities of owners The owners of the radiation safety of the irradiation apparatus fully responsible for radiation protection and safety should be developed outline, specify the person in charge of radiation protection, with Equipment or hiring qualified experts. 8.3 Radiation Protection Leader Owners should be set radiation protection and safety agencies, and specify the person responsible for radiation protection, and give it the appropriate rights, if needed for the operation and spoke When there is a potential conflict between the Radiation Safety, a priority of radiation safety. The person in charge of radiation protection responsibilities include. --- Provide operating instructions to all operators, maintenance personnel and other related personnel, training assessment and confirm that they have Master, follow these instructions; --- Inlet passage control zone management; --- Ensure radiation worker radiation doses to meet the requirements of 4.1.2; --- Verification arrangements radiation monitoring instruments; --- Check the service records of radioactive sources and recording equipment; --- Development of radiation safety testing program and organize the implementation; --- Monitor individual dosimeters distribution and recovery, evaluate dose monitoring results; --- Organize and conduct regular safety inspection procedures; --- Appears radiation safety problems and timely reporting; --- Development of contingency plans, arrange periodic drills to ensure their suitability and effectiveness; --- Prepare an annual assessment report irradiator safety and protection conditions. 8.4 qualified experts 8.4.1 owners employ more than 5 years of radiation safety management experience and professional background and the title of senior staff as qualified experts. Qualified experts to make recommendations on radiation safety within the regulatory issues related to the scope, should not bear the responsibility of the owners. 8.4.2 Qualified experts should provide advice and assistance when the owner needs. --- Optimization of radiation protection; --- Dosimetry and radiation monitoring; --- Survey irradiation overdose events; ---staff training; --- Radiation safety assessment and contingency plans; --- New construction, renovation, expansion plans irradiator; ---Quality Control; --- Emergency treatment. 8.5 Safety Culture Owners should cultivate and maintain good safety culture to ensure that. --- Development of radiation protection and safety in the first place policies and procedures; --- To discover and address the impact of radiation protection and safety issues, the approach to be consistent with the importance of the issue; --- Specifically related personnel (including senior executives) of the radiation protection and safety responsibility, radiation workers should be trained and have the There are suitably qualified; --- Clear relationship between radiation protection and safety and responsibility in decision-making; --- Organization and establish effective channels of communication to keep radiation protection and safety information in all levels and sectors between owners Smooth.9 Radiation Safety Testing9.1 routine daily inspection should include at least the following. a) Working status indicator; b) Radiation safety interlock control room display condition; c) Lift the source and delivery system conditions; d) personal alarm dosimeters and portable Dose Monitor; e) a reservoir well water level; f) ventilation systems. 9.2 regular monthly examination should include at least the following. a) irradiating an indoor stationary radiation monitors. b) a source of emergency lowering system. c) source and a guide wire rope hoist, conveyor systems. If the tether appear overused phenomenon, should be replaced. d) fill the water replenishment should check whether it is normal. As an exception, you should check wells for leaks and check the water supply system operation situation. 9.3 General six months examination should include at least the following. a) with annual maintenance of detection; b) water quality and pollution detection; c) environmental radiation levels; d) all the equipment and automatic control system. Detecting radiation source means to change or add source 9.4 shall include at least the following. a) a reservoir of water and well water well radioactivity levels; b) the number of radioactive sources; c) loading a source container surface dose rate and Pollution; d) Source tool handling and lifting equipment condition; e) Individual Dose operator. 9.5 Radiation detection equipment installed after the source should include at least the following. a) a source 24h after the radioactivity level of well water; b) a source at the working position, the dose to the surrounding environment and workplace monitoring; c) source in storage position on the side of a reservoir Inoue and radiation dose monitor chamber. 9.6 The operating organization should do more safety testing, the use of standardized forms records and annual assessment. Records should be kept to the irradiator Retired. Managed 10 radioactive sources 10.1 radioactive sources into the unit should hold a license, fill radioisotope import or transfer approval form, after the approval of the regulatory authorities Before transfer. Around 10.2 installation source and should make a detailed inventory of the accounting registration (including the type of radioactive sources, the number of coding each one source, and daily activity Period, the location of the source frames, etc.), installed source personnel, radiation protection and the executives responsible for the signing, record-keeping to decommissioning. 10.3 should be checked annually shelves radioactive source without loss, make a record. 10.4 Source retired after delivery or return to the reservoir manufacturer shall filing procedures and records (including radioactive source coding, activity and date, go Storage and delivery to date). The records shall be kept to the irradiator retired. 10.5 sources has reached its useful life specified by the manufacturer of the safe use of the period should be allowed to retire and promptly sent to storage. 10.6 Irradiation means the owners of the safety and security of radioactive sources responsible for its duties should include. a) special attention to security decommissioning radioactive sources; b) lost, stolen or missing radioactive sources should report the relevant departments in accordance with regulatory requirements. Retired 11 irradiator 11.1 life Irradiators life of 40a. 11.2 Extended Run If you reach but the owners request an extension of life, it shall submit the regulatory safety evaluation report and other supporting information used by extension, the After review approval, it may postpone the operation. 11.3 mandatory retirement For various reasons, can not repair the damaged device should be forced its retirement......Tips & Frequently Asked Questions:Question 1: How long will the true-PDF of GB 10252-2009_English be delivered?Answer: Upon your order, we will start to translate GB 10252-2009_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 GB 10252-2009_English with my colleagues?Answer: Yes. 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