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GB 12711-2018 English PDF

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GB 12711-2018: Standard of safety for low and intermediate level solid radioactive waste packages
Status: Valid

GB 12711: Historical versions

Standard IDUSDBUY PDFLead-DaysStandard Title (Description)Status
GB 12711-2018179 Add to Cart 3 days Standard of safety for low and intermediate level solid radioactive waste packages Valid
GB 12711-1991279 Add to Cart 3 days Standard of safety for low and intermediate-level solid radioactive wastes packages Obsolete

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GB 22128   GB/T 32885   GB/T 32357   GB/T 45754   GB/T 32124   

Basic data

Standard ID: GB 12711-2018 (GB12711-2018)
Description (Translated English): Standard of safety for low and intermediate level solid radioactive waste packages
Sector / Industry: National Standard
Classification of Chinese Standard: Z05
Word Count Estimation: 9,923
Date of Issue: 2018-11-19
Date of Implementation: 2019-03-01
Older Standard (superseded by this standard): GB 12711-1991
Regulation (derived from): Ministry of Ecology and Environment Announcement No.50 of 2018; National Standard Announcement No.15 of 2018
Issuing agency(ies): State Administration for Market Regulation, China National Standardization Administration

GB 12711-2018: Standard of safety for low and intermediate level solid radioactive waste packages


---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.
(Low and medium level radioactive solid waste package safety standards) 1ICS 13.030 Z 05 National Standards of People's Republic of China Replace GB 12711-1991 Low and medium level radioactive solid waste package safety standards Standard of safety For low and intermediate level solid radioactive waste packages Published on.2018-10-29 2019-3-1 Implementation State Market Supervisory Administration Ministry of Ecology and Environment release

Content

Foreword..II 1 Scope.1 2 Normative references.1 3 Terms and Definitions 1 4 General principles. 2 5 Basic requirements for low and medium level radioactive solid waste package contents. 2 6 Basic requirements for design and manufacture of low and medium level radioactive solid waste packaging containers.3 7 Low and medium level radioactive solid waste package surface dose rate limit..4 8 Low and medium level radioactive solid waste package surface pollution limit 4 9 Tests and tests 4 10 Waste storage, transportation and disposal operations..5 11 Emergency Planning and Preparation..5 12 Quality Assurance..5

Foreword

In order to implement the Environmental Protection Law of the People's Republic of China, the Law of the People's Republic of China on Prevention and Control of Radioactive Pollution, The Law of the People's Republic of China protects the environment, protects human health, and regulates the safe management of low- and medium-level radioactive solid wastes. This standard is formulated. This standard specifies the basic safety requirements for low- and medium-level radioactive solid waste packages, including low- and medium-level radioactive solid packaging containers. Basic requirements for the safety of outer packaging (radiation shielding) containers and container containers. This standard is a revision of the "Safety Standard for Packaging of Low and Medium Level Radioactive Solid Wastes" (GB 12711-1991). China Institute of Atomic Energy. Compared with the original standard, the main changes are as follows. -- Modifications to the surface dose rate requirements for waste packages of general concern; -- A small number of additions and deletions have been made to the "referenced documents" and "terms and definitions"; -- Rewrote the "Basic Requirements for Containments in Waste Packages" and "Basic Requirements for Design and Manufacture of Packaging Containers"; -- The provisions of the "Emergency Planning and Preparation" and "Quality Assurance" chapters have been added; -- Added a chapter on "Testing and Testing"; -- Added provisions to minimize waste and safety of waste packages. This standard was first published in.1991 and this is the first revision. GB 12711-1991 shall be abolished from the date of implementation of this standard. This standard is formulated by the Radiation Source Safety Supervision Department of the Ministry of Ecology and Environment, the Nuclear Facilities Safety Supervision Department, and the Science and Technology Standards Department. This standard is mainly drafted by. China Institute of Atomic Energy. This standard has been implemented since March 1,.2019. This standard is explained by the Ministry of Ecology and Environment. Low and medium level radioactive solid waste package safety standards

1 Scope of application

This standard specifies the basic safety requirements for low- and medium-level radioactive solid waste packages, and stores low- and medium-level radioactive solid waste packages. Disposal and transportation operations have been requested. This standard is applicable to the preparation of low and medium level radioactive solid waste generated by nuclear facilities and nuclear technology utilization units during operation and decommissioning. After the waste package. This standard does not apply to waste packages after radioactive tailings slag and waste radioactive sources have been prepared.

2 Normative references

The following documents are indispensable for the application of this document. For dated references, only the dated version applies to this article. Pieces. For undated references, the latest edition (including all amendments) applies to this document. Safety regulations for near-surface disposal of low- and medium-level radioactive solid wastes GB 9132 GB 11806 Safe Transport Procedure for Radioactive Material GB 11928 Provisional storage regulations for low and medium level radioactive solid waste GB/T 15219 Quality assurance of transportation and packaging of radioactive materials GB 18871 Basic standards for ionizing radiation protection and radiation source safety EJ 914 low and medium level radioactive solid waste concrete container EJ 1042 low and medium level radioactive solid waste container steel drum EJ 1076 low and medium level radioactive solid waste container steel box EJ 1186 Characterization of radioactive waste bodies and waste packages "Radioactive Waste Classification" Ministry of Environmental Protection Ministry of Industry and Information Technology National Defense Science and Technology Industry Bureau Announcement No. 65 of.2017

3 Terms and definitions

3.1 waste package waste package The sum of the waste body and its packaging container. The waste package delivered for transportation is called a waste package. 3.2 packaging container package container Containers containing solidified or fixed and other treated radioactive waste. 3.3 Overpack container over-package container When the surface dose rate of the waste package exceeds the management limit, a packaging container that is attached to the outside of the waste package to reduce the radiation level, or a waste package A packaging container that is damaged and attached to the outside of the waste bag. Some outer packaging containers are used multiple times; some are disposed together and used only once. 3.4 container container To facilitate the transportation, handling, storage and disposal operations, a plurality of packaging containers for packaged waste packages are assembled. Most container containers are used The transportation process is used multiple times; there are also a few that are disposed of together and used only once. 3.5 Effective loading factor efficient loading factor The volume of waste contained in the waste package as a percentage of the total volume of the waste package. 3.6 Dispersible waste Non-monolithic, dispersible waste that is prone to pollution and spread, such as incineration ash, evaporation residue, waste ion exchange resin, waste Carbon powder, etc. 3.7 high integrity container high integrity container It is expected to contain containers for low- and medium-level radioactive solid waste contained in it for more than 300 years. High finish Integrity containers can be made of different materials (such as concrete, ductile iron, high density polyethylene or composites). 3.8 load combination load combination a combination of forces, such as the weight of the container, the gravity load of the contents under normal operating conditions or under test conditions, temperature gradients or The combination of thermal expansion force, stacking and static load of the maximum load-bearing layer of the covering, and the dynamic load of the force during transportation or hoisting.

4 General principles

4.1 All units that produce low- and medium-level radioactive solid waste shall have measures for safe, reliable and economical packaging of radioactive waste. The radioactive material is released into the environment in an unacceptable amount to ensure that the public and staff exposure dose does not exceed the requirements of GB 18871 Limits, and as low as reasonably achievable. 4.2 Wastes should be collected and classified, preferably in appropriate packaging containers, to avoid repeated replacement of containers for reversed waste. 4.3 The waste package shall meet the requirements for handling, storage, disposal and transportation, and it is convenient to operate and ensure that it can be returned from the storage within the specified storage period. It is sent to disposal; and it can function as an engineering barrier in multiple barrier systems within a certain period of time after disposal. 4.4 For waste packages whose surface dose rate exceeds the limit, in order to reduce the exposure dose of the staff, it can be packaged in an outer packaging container and then moved. Transportation and/or transportation. In order to facilitate the transportation operation of the waste package and improve the work efficiency, the container can be used for container handling and container transportation. 4.5 Waste should be properly volume-reduced in advance, and containers with high effective filling factor should be selected to reduce the storage, transportation and disposal of waste. burden. 4.6 In principle, waste packaging should be in a standard series of containers. For large pieces of waste generated from decommissioning and overhaul, the cost of cutting and disintegration is too great. Non-standard large containers can be used for reasons such as inconvenience in cutting. However, the use of such containers should meet safety requirements and comply with transportation, storage and disposal. Relevant regulations.

5 Basic requirements for low and medium level radioactive solid waste package contents

5.1 The specific activity of the waste contained in the packaging container shall be in accordance with the radioactive level of low- and medium-level radioactive solid waste. 5.2 The waste contained in the container should be as dense as possible and filled with the container. Evaporation residue, mud, incineration ash, waste ion exchange resin, etc. In addition to the use of high integrity containers, bulk waste should be cured or otherwise treated prior to disposal. Small incompressible solids and After the cut solid parts and the super compacted waste cake are loaded into the container, they should be fixed by pouring cement mortar before disposal. 5.3 When the waste is contained, gas (such as radioactive gas) is generated. The packaging container should be considered to reserve appropriate space or other to avoid overpressure. Measures. 5.4 It is not allowed to be loaded in the waste packaging container a) explosive substances or substances that can react violently when in contact with water; b) spontaneous combustion or flammable substances; c) strongly corrosive substances; d) untreated animal carcasses and pathogen-containing substances; e) Non-radioactive highly toxic substances. 5.5 The volume of free liquid in the waste package should be less than 1% of the volume of solid waste. 5.6 The amount of fissile material contained in the waste package should be less than 15g.

6 Basic requirements for packaging containers for low and medium level radioactive solid waste

6.1 Low and medium level radioactive solid waste packaging containers except steel drums (EJ 1042) and steel boxes (EJ 1076) In addition to concrete containers (EJ 914), other materials and structures that meet the requirements for handling, handling, storage and disposal are also available. Containers, such as high integrity containers, polymer impregnated concrete and cast iron containers, and smelting and recycling of qualified steel with radioactively contaminated scrap steel Container made of wood. 6.2 Low- and medium-level radioactive solid waste containers should be based on waste characteristics, state-scheduled maturity periods, environmental conditions of temporary storage sites, Transportation methods, disposal methods, and anticipated accidents are designed and manufactured to meet the following requirements. a) Strong and strong, able to withstand various load combinations under normal working conditions, and can withstand loading, unloading, handling, storage and transportation Damage that occurs under various accident conditions that do not exceed the design basis accident; b) The cover is easy to operate and has good sealing performance. The cover will not be opened due to internal pressure; c) Conveniently tamping and stacking, it can be stably fixed on the transport vehicle. Acceleration, vibration and resonance effects encountered in conventional transportation, Will not damage the integrity of the waste package, nuts, bolts/or other fasteners will not loose or fall off; d) the structure and materials of the container are compatible with the physical and chemical properties of the contained waste and environmental conditions (such as temperature, humidity, air atmosphere, etc.). Can withstand the effects of temperature and pressure that may be encountered during normal operation, as well as the effects of temperature and pressure under the conditions of disposal; e) corrosion, radiation and bioerosion protection, ensuring that the container can be retrieved within the storage period specified by the design; f) The appearance is smooth and flat, no water and water accumulation, easy to decontaminate; g) The waste package can be handled conveniently and safely, loading and unloading operations; h) Reasonable material selection, simple structure, economical and durable. 6.3 Steel containers for low- and medium-level radioactive solid waste should pay attention to the protection of coatings (such as spray paint, sprayed zinc layer, etc.). Paint The layer is uniform and has a suitable thickness. In addition to considering the corrosive effect of the outer wall of the container, attention should also be paid to the corrosive effect of the internal waste on the inner wall of the container. 6.4 The outer packaging container shall meet the requirements of radiation shielding and match the size of the internal waste container to safely handle the built-in waste package. If the outer packaging container is to be used as a disposal container for one-time use, consider filling the gap between them. 6.5 Containers should be of appropriate size, well matched to the internal waste package, have a high effective filling factor, and are easy to safely handle the internal waste package. If the container is to be used as a disposal container once, consider filling the gap inside the container. 6.6 The outer surface of the waste package shall be radioactively marked and numbered. The radioactive sign is subject to the provisions of GB 11806. The waste pack number is set in the package The lower half of the lower half of the device is a black positive Arabic numeral with a font height of 1/7 to 1/10 of the height of the container. This sign and number should wake up Eye, clear, water resistant, long-term preservation. Barcodes can also be used for waste packages. 6.7 Low and medium level radioactive solid waste packages are mostly industrial packages or “Type A packages” as specified in GB 11806, and a few are classified as Type B goods. package. The packaging container for the type A package is yellow, and the packaging container for the type B package is orange.

7 Low and medium level radioactive solid waste package surface dose rate limit

7.1 Low- and medium-level radioactive solid waste packages for direct handling, handling, storage and disposal, any point on the outer surface The dose rate should be ≤2.0mSv/h. If this limit is exceeded, additional shielding (such as outer packaging containers) or remote operation should be used. 7.2 The low- and medium-level radioactive solid waste packages for off-site transportation shall meet the relevant requirements of GB 11806.

8 Low and medium level radioactive solid waste package surface pollution limit

The surface contamination level of low and medium level radioactive solid waste packages should be lower than the limits listed in Table 1. Table 1 Surface contamination limits for low and medium level radioactive solid waste packages β, γ emitter, low toxicity α emitter 4 Bq/cm2 Other α emitters 0.4 Bq/cm2 Note. It can be judged by the average value of non-fixed pollution taken on any 300cm2 area of any part of the surface.

9 Test and inspection

9.1 Waste packaging containers, outer packaging containers and container containers shall be tested and inspected in accordance with relevant regulations. 9.2 Product quality inspection of steel drums, steel boxes and concrete containers shall be carried out in accordance with EJ 1042, EJ 1076 and EJ 914, respectively. Factory capacity The device shall meet the quality inspection requirements, and the product quality inspection certificate and product inspection card shall be submitted at the time of shipment. 9.3 According to GB 11806 and EJ 1186, the test items for industrial packages or type A packages include. a) water spray test; b) free fall test; c) stacking test; d) Through the test. The above test items are carried out in accordance with the provisions of GB 11806. 9.4 The test items for type B packages shall be carried out in accordance with the relevant provisions of GB 11806. 10 Waste storage, transportation and disposal operations 10.1 The operation of waste storage, transportation and disposal shall be carried out by qualified personnel, and the radiation protection personnel shall be responsible for supervision. 10.2 Suitable loading and unloading equipment and tools should be used for loading and unloading operations, and illegal operations are not allowed. 10.3 The storage and disposal of waste packages should be piled up neatly according to the set position to prevent accidents from falling. 10.4 The operator should wear a personal dosimeter and wear the necessary protective clothing. 10.5 The waste package storage operation shall carry out the relevant provisions of GB 11928; the waste package transport operation shall comply with the relevant provisions of GB 11806; The waste package disposal operation implements the relevant provisions of GB 9132. 10.6 The operating personnel and the public's exposure dose limits shall be subject to the relevant provisions of GB 18871. 11 Emergency planning and preparation 11.1 There should be contingency planning and preparation for the operation of waste storage, transportation and disposal. 11.2 Storage and handling of waste packages should be carried out with appropriate tools to avoid falling and falling and damaging the waste packaging container. 11.3 Unwanted damage to the waste package and leakage of radioactive materials, or suspected damage and leakage of radioactive materials When the protective measures personnel approach the waste package, the radiation protection personnel will detect the pollution range and pollution level as soon as possible. When found to have caused the environment When contaminating, the contaminated area should be delineated and marked. Leaked radioactive materials should be collected; the resulting pollution should be decontaminated. 11.4 Damaged waste packages should be repaired or replaced, or a new container on the original packaging container to prevent leakage and For the expansion of pollution, radiation protection personnel are responsible for supervising the treatment. 11.5 When the human body is found to be contaminated, decontamination of the human body should be carried out under the guidance of radiation protection or medical personnel, and medical treatment should be carried out as needed. The causes and treatment of waste package accidents shall be reported to relevant department......
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