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GB 11806-2019: Regulations for the safe transport of radioactive material
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Basic data | Standard ID | GB 11806-2019 (GB11806-2019) | | Description (Translated English) | Regulations for the safe transport of radioactive material | | Sector / Industry | National Standard | | Classification of Chinese Standard | F73 | | Classification of International Standard | 13.300 | | Word Count Estimation | 79,723 | | Date of Issue | 2019-04-04 | | Date of Implementation | 2019-04-01 | | Issuing agency(ies) | State Administration for Market Regulation, China National Standardization Administration | GB 11806-2019: Regulations for the safe transport of radioactive material---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 the safe transport of radioactive material
ICS
CCS
Replace GB 11806-2004
Radioactive articles safe transport procedures
Published on.2019-02-15
Implementation of.2019-04-01
Ministry of Ecology and Environment
State market supervision and administration
National Standards of People's Republic of China
release
table of Contents
Foreword...1
1 Scope...1
2 Normative references...1
3 Terms and Definitions...1
4 General requirements...6
4.1 Radiation protection...6
4.2 Emergency Response...6
4.3 Quality Assurance...6
4.4 Compliance Guarantee...6
4.5 Special Arrangements...6
4.6 Non-conformance...7
4.7 Training...7
5 limits...8
5.1 Basic values of radionuclides...8
5.2 Determination of the basic value of radionuclide...8
5.3 Radiation level limits...9
5.4 Surface contamination level limits...9
5.5 Transport Index and Critical Safety Index Limits...9
6 Requirements for radioactive items...9
6.1 Low specific activity items...9
6.2 Surface Contaminant Body...10
6.3 Special forms of radioactive materials...11
6.4 Low Dispersion Radioactive Materials...11
6.5 Exceptional fissile material...11
6.6 Uranium hexafluoride...12
7 Packaging and package requirements...12
7.1 Classification of packages...12
7.2 General requirements for all packaging and packages...14
7.3 General requirements for IP-3, Type A, Type B and Type C packages...14
7.4 Additional requirements for air cargo packages...15
7.5 Additional Requirements for Industrial Packages...15
7.6 Additional requirements for uranium hexafluoride package...16
7.7 Additional Requirements for Type A Packages...17
7.8 Additional Requirements for B(U) Packages...17
7.9 Additional requirements for B(M) type packages...18
7.10 Additional Requirements for Type C Packages...18
7.11 Additional requirements for fissile material packages...19
8 Transportation requirements...22
8.1 Radioactive Article Name and UN Number...22
8.2 Requirements before shipment of goods...23
8.3 Determination of transportation index and critical safety index...23
8.4 Requirements for transportation and intermediate storage...24
8.5 Packing and assembly packaging classification...28
8.6 Marks, signs and signs...29
8.7 Shipper's Duties...31
8.8 Carrier retains and obtains shipping documents...33
8.9 Customs Operations...33
8.10 Undeliverable consignment...33
9 Items that need to be approved...33
9.1 Overview...33
9.2 Design Approval Items...34
9.3 Approval of Transportation Activities...36
Appendix A (informative)...38
Appendix B (Normative Appendix)...48
Appendix C (Normative Appendix)...66
Appendix D (Normative Appendix)...71
1 Introduction
To implement the Law of the People's Republic of China on Environmental Protection, the Law of the People's Republic of China on Prevention and Control of Radioactive Pollution,
The Nuclear Safety Law of the Republic and the Regulations on the Safety Management of the Transport of Radioactive Materials, to prevent and control radioactive pollution and to improve environmental quality,
Standardize the management of radioactive materials transportation and formulate this standard.
This standard was first published in 1989 and first revised in.2004. This is the second revision. Radioactive material
Compared with the Safe Transportation Regulations (GB 11806-2004), the main revisions are as follows.
-- The standard name is changed to "Safety Transportation Regulations for Radioactive Materials", and combined with the above and below contents, the standard part of the "radiation"
"Sexual substances" was changed to "radioactive articles";
- Increased radioactive activity limits for exempted consignments for individual radionuclides in instruments or products.
The basic value of the radionuclide is replaced and the calculation conditions and requirements for this substitution are explained;
-- Modifications to the definition, classification, limits and related requirements for “fissile materials”;
-- Amend the original standard “Table 8 UN number, special freight name and description and incidental hazards”;
-- Move the radionuclide activity limit table from the original standard from the text to the normative appendix B;
The procedure is moved to the normative Appendix C.
This standard has been revised to adopt the International Atomic Energy Agency (IAEA) Specific Safety Requirements No.SSR-6..2012
The annual edition of the Regulations on the Safe Transport of Radioactive Materials.
Compared with SSR-6..2012, the technical content of this standard is consistent with the adopted international standards, with only minor modifications.
There are more adjustments in the structure. The main changes are as follows.
-- Removed the preface to SSR-6..2012;
-- Removed the "Introduction" section of Chapter 1 of SSR-6..2012 and replaced it with Chapter 1 "Scope" of this standard;
-- Combining China's national conditions and practices, the domestic and international connections to the "Chapter IX matters requiring approval" have been carried out;
-- Replace some of the other international standards cited in SSR-6..2012 with the corresponding Chinese standards;
--Delete SSR-6. Appendix I of the.2012 “Summary of Approval and Advance Notice Requirements”, Appendix II “Conversion Factors and Words”
"Head" and Appendix III "Summary of consignments to be transported by exclusive use";
-- Added Appendix A. Appendix A lists the comparison of this standard with the SSR-6..2012 chapter number.
This standard is formulated by the Department of Environmental Protection's Radiation Source Safety Supervision Department and the Department of Regulations and Standards.
This standard was drafted. Nuclear and Radiation Safety Center of the Ministry of Environmental Protection.
This standard was approved by the Ministry of Ecology and Environment on January 3,.2019.
This standard has been implemented since April 1,.2019. From the date of implementation, GB 11806-2004 will be abolished at the same time.
This standard is explained by the Ministry of Ecology and Environment.
1 Radioactive articles safe transport procedures
1 Scope
This standard specifies the safety requirements for the transport of radioactive materials under normal conditions of transport, normal conditions of transport and conditions of transport accidents. This standard
The transportation requirements for the quasi-medium include the design, manufacture and maintenance of the package, as well as the preparation, consignment, loading and carrying of the package (including midway).
Storage) and the receipt and unloading of the final arrival of the package.
This standard applies to any means of transport of radioactive material (including radioactive material concomitantly used) on land, water and air.
This standard does not apply to.
a) radioactive material that has become an integral part of the means of transport;
b) transporting radioactive materials that do not involve public roads or railways within the unit, ie in-plant transportation;
c) radioactive material that has been implanted or injected into human or living animals for diagnosis or treatment;
d) persons present in the body or in vitro due to accidental or deliberate ingestion of radioactive material or radioactive contamination
Radioactive material;
e) radioactive material in consumer products that have been approved by the relevant government authorities and sold to end users;
f) processed natural substances and ores containing natural radionuclides, and the activity concentration of such substances does not exceed this standard
10 times the exemption value specified in 5.1 to 5.2. For natural substances containing natural radionuclides that are not in a long-term equilibrium state
And ore, the concentration of its activity should be calculated in accordance with 5.2.3;
g) any non-radioactive solid with radioactive material on its surface but not exceeding the surface contamination level specified in 3.13 of this standard
object.
When transporting radioactive materials carries additional risks or is shipped with other dangerous goods, it should also comply with the transport of dangerous goods.
The relevant provisions.
2 Normative references
The following documents are indispensable for the application of this document. For dated references, only the dated version applies to this
file. For undated references, the latest edition (including all amendments) applies to this document.
General requirements and classification of GB 4075 sealed radioactive sources (GB 4075 -2009, ISO 2919.1999, MOD)
GB/T 15849 Sealing radioactive source leak test method (GB/T 15849-1995, EQV ISO 9978.1992)
Technical requirements and test methods for GB/T 5338 series 1 - Part 1. General purpose containers (GB/T 5338-2002, IDT
ISO 1496-1.1990)
GB 18871 Basic standards for ionizing radiation protection and radiation source safety
ISO 7195 transport of uranium hexafluoride (UF6)
ST/SG/AC.10/1/Rev.17 United Nations Recommendations on the Transport of Dangerous Goods
3 Terms and definitions
The following terms and definitions apply to this standard.
3.1
Basic radionuclide values
The basic value of radionuclide refers to the activity value derived from the type of package and other management requirements, especially A1 and
A2. Al means the activity value of a special form of radioactive material listed in Appendix B, Schedule B1 or derived in Chapter 5,
The activity limit specified for the determination of the requirements of this standard. A2 means the one listed in Schedule B1 of Appendix B or in Chapter 5.
The activity value of the radioactive material other than the derived special form radioactive material is specified for the determination of the requirements of this standard.
Radioactivity limit.
23.2
Unilateral approval of unilateral approval
The design of a package is subject to approval by the relevant government department of the country of design.
3.3
Multiparty approval
Except for the approval of the relevant government department of the original design country or the original shipping country, the consignment to be transported is on the way or arriving at any of them.
In his country, it should also be approved by the relevant government departments of these countries. The term “via or arrival” does not include “flying over”, ie the use of aircraft
Such approval and notification requirements do not apply to the country when transporting radioactive material over a country and is not prepared to stay in that country.
3.4
Compliance guarantee
A series of measures and actions taken by relevant government departments to ensure that the provisions of this standard are observed in practice.
3.5
Quality assurance
Is a systematic outline for the management and supervision of organizations or units involved in the transport of radioactive materials, which is intended to
Provide sufficient credibility to the safety requirements specified in this standard.
3.6
Radioactive material
Any item in the consignment that contains radionuclides and whose activity concentration and total radioactivity exceed the values specified in 5.1 to 5.2.
3.7
Radioactive content radioactive contents
Radioactive items in the package together with solids, liquids and gases that have been contaminated or activated.
3.8
Fissile nuclides and fissile material
The fissile nuclides refer to uranium-233, uranium-235, thorium-239, and thorium-241. Fissile material means any fissile nuclides containing any of the above
material. This definition of fissile material does not include.
a) unirradiated natural or depleted uranium;
b) irradiated natural uranium or depleted uranium only in thermal neutron reactors;
c) materials containing less than 0.25 g of total fissile nuclide;
d) any combination of the above a), b) and/or c).
The above exclusion is only if there are no other fissile nuclide in the consignment in the package or in the unpackaged transport.
Effective.
3.9
Special form radioactive material
A solid radioactive article that is not diffused or a seal containing radioactive material.
3.10
Low dispersible radioactive material
a solid radioactive article, or a solid radioactive article contained in a seal, whose dispersion is limited and not present
Powdery.
3.11
Specific activity
Refers to the unit mass of radionuclide activity, also known as activity concentration.
The specific activity of a substance refers to the activity per unit mass in which the radionuclide is substantially uniformly distributed.
3.12
Low specific activity material (LSA)
3 According to its physical characteristics, it refers to radioactive articles with limited specific activity, or radioactive articles with an estimated average specific activity below the limit.
When determining the average specific activity, the outer shielding material around the low specific activity article should not be considered.
3.13
Surface contamination
There are more than a certain amount of radioactive material on the surface. for β and γ emitters and low toxicity α emitters, the amount exceeds 0.4
Bq/cm2, or for all other alpha emitters, the amount exceeds 0.04 Bq/cm2.
Surface contamination includes non-fixed and fixed contamination.
- Non-fixed pollution means pollution that can be removed from the surface under normal conditions of transport;
- Fixed pollution means pollution other than fixed pollution.
3.14
Surface contaminated body (SCO)
A solid object that is not radioactive but has radioactive material on its surface.
3.15
Unirradiated uranium unirradiated uranium
The uranium content of uranium-235 per gram does not exceed 2 × 103 Bq, the content of fission products per gram of uranium-235 does not exceed 9 × 106 Bq and per gram of uranium
Uranium-236 in -235 contains no more than 5 x 10-3 g of uranium.
3.16
Natural uranium, depleted uranium, enriched uranium - natural, depleted, enriched
Natural uranium refers to uranium containing natural uranium isotope ratio obtained by chemical separation. Ure-238 accounts for 99.28% by mass.
Uranium-235 accounts for about 0.72%).
Depleted uranium refers to uranium containing less than uranium-235 mass percent of natural uranium.
Enriched uranium means uranium containing more than uranium-235 by mass.
The mass percentage of uranium-234 contained in the above three uranium is very small.
3.17
Unirradiated 钍unirradiated thorium
The uranium-233 content per gram of bismuth-232 does not exceed 10-7 g of strontium.
3.18
Low toxicity alpha emitters
钍-228 contained in natural uranium, depleted uranium, natural strontium, uranium-235 or uranium-238, strontium-232, ore or physicochemical concentrate
And 钍-230 and alpha emitters with a half-life of less than 10 d.
3.19
Packaging packaging
Refers to one or more containers and any other components or materials in the container that are required for containment and other security functions.
3.20
Design
Clear description of special forms of radioactive material, low-dispersion radioactive material, exceptional fissile material as specified in 6.5.2, package or packaging
Information on items. These materials may include technical specifications, engineering drawings, reports demonstrating compliance with regulatory requirements, and other relevant
file.
3.21
Constraint system
A combination of fissile material and packaging components specified by the designer and approved by the relevant government authorities for maintaining criticality.
3.22
Containment system
A combination of packaging components for containment of radioactive articles during transport as determined by the designer.
43.23
Maximum normal operating pressure
Ambient temperature and sun equivalent to no ventilation during transportation, external cooling without auxiliary system, or no operational management
Under irradiation conditions, the maximum pressure above the standard atmospheric pressure that may be generated in the system during the one-year period is contained.
3.24
Package package
A general term for the shipping package and its radioactive content. The following types of packages covered by this standard shall comply with the emissions of Chapter 7.
Sexual activity limits and classifications, and meet the corresponding requirements.
a) Exceptional package;
b) industrial packages;
c) Type A package;
d) B (U) type package;
e) B (M) type package;
f) Type C package.
Packages containing fissile material packages or uranium hexafluoride should meet the additional requirements.
3.25
Tank (tank) tank
Tank (tank) means a tank that can be transported, including cans, road tankers or tanks for railway tankers, or other solids, liquids,
A gas container in which the capacity for transporting gas is not less than 450 L.
3.26
Collection wrapper
In order to facilitate loading and unloading and stacking during transportation, a single consignor is used to contain one or more packages and synthesize a unit for outsourcing.
set.
3.27
Shipper consignor
The person or organization that submits the consignment to the transport.
3.28
Consignee consignee
The person or organization that receives the consignment.
3.29
Carrier carrier
An individual or organization that undertakes the transport of radioactive materials using any means of transport.
3.30
Consignment consignment
The shipper submits a package or multiple packages, or a batch of radioactive items for transportation.
3.31
Radiation level
The corresponding dose rate expressed in mSv/h or μSv/h.
3.32
Radiation protection programme
Means a document that systematically describes radiation protection management and measures.
3.33
Transport index
5 pairs of packages, collective packaging or cargo containers, or unpackaged LSA-I or SCO-I, the specified transport index (TI) is used for control
A value for radiation exposure.
3.34
Critical safety index
The criticality safety index (CSI) given for packages, collection packages or cargo containers containing fissile material is used to control the loading
A value for the accumulation of fissile material, parcels, and cargo containers.
3.35
Shipment
The specific transportation of the consignment from the place of departure to the destination.
3.36
Special arrangement
Some measures approved by the relevant government authorities, according to which they can transport consignments that do not meet all the applicable requirements of this standard.
goods.
3.37
Exclusive use of exclusive use
A single shipper uses a single piece of transport or a large cargo container and follows the shipper’s or consignee’s requirements.
Transportation of the line, including loading, unloading and shipping of the starting point, midway and destination.
3.38
Transportation conveyance
Transportation means.
a) various vehicles used for road or rail transport;
b) any type of ship used for water transport, or any cargo hold, compartment or defined deck area of the ship;
c) Various aircraft used for air transportation.
3.39
Vehicle vehicle
Road vehicles (including articulated vehicles, that is, a combination of tractors and trailers) or rail cars or railway wagons. Every trailer should
It is considered a separate vehicle.
3.40
Cargo aircraft
Means any aircraft carrying cargo or property other than a passenger aircraft.
3.41
Passenger aircraft
Carrying out employees of crew members, operators with official status, representatives authorized by the relevant national authorities or consignments or other
The aircraft of any person other than the escort of the goods.
3.42
Ship vessel
Various sea or inland watercraft for cargo.
3.43
Freight container
A cargo container is a type of transportation device that is durable and strong enough for reuse. Cargo containers are specially designed
To transport goods in one or more modes of transport and without reloading in the middle, the design is equipped to be fixed and/or easy to install
Parts for unloading and other purposes. The term "cargo container" does not include vehicles.
Small cargo containers are cargo containers with an internal volume of not more than 3 m3. Large cargo container means internal volume greater than 3
M3 cargo container.
63.44
Intermediate bulk container
The following easy-to-handle packages.
a) the volume is not more than 3 m3;
b) using mechanical loading and unloading;
c) According to the performance test, it can resist the stress generated during loading and unloading and transportation.
3.45
Defined deck area
The area designated for the accumulation of radioactive material on the open deck of the ship, or on the deck of a ro-ro ship or ferry-parked vehicle.
4 General requirements
4.1 Radiation protection
4.1.1 The dose received by personnel should be lower than the dose limit specified in GB 18871. Protection should be optimized, that is, considering the economy and society
After the factor, the size of the individual dose, the number of people exposed, and the exposure caused by the individual’s dose below the dose-constrained value
The possibility is kept as low as reasonably achievable. Measures should be taken from organizational structures and systems, and transport and other
The relationship between activities.
4.1.2 The shipper should develop a radiation protection program. The measures to be taken in the outline should be compatible with the size of the radiation exposure and the likelihood of exposure.
The outline should reflect the requirements for emergency response and should also reflect the requirements of 4.1.1, 4.1.3, 4.7.1 and 8.4.1.1. The text of the outline should follow
It can be checked by relevant government departments.
4.1.3 Occupational exposure to transport activities.
a) When the effective dose in a year is never more than 1 mSv, no special working methods are required, and no detailed monitoring is required.
Develop a dose assessment plan and save personal records;
b) Personal dose monitoring should be performed whenever possible when the effective dose for the year is expected to be between 1 mSv and 6 mSv. response
The evaluation of the occupational exposure of such personnel shall be based on the results of individual monitoring or workplace monitoring;
c) Personal dose monitoring and evaluation should be performed when the effective dose for the year is expected to exceed 6 mSv.
Relevant records should be kept for personal monitoring or workplace monitoring.
4.1.4 The relevant government department shall stipulate the periodic assessment requirements for the radiation dose of personnel caused by the transportation of radioactive materials to ensure protection and
The safety system complies with the requirements of GB 18871.
4.2 Emergency response
4.2.1 Once an accident or minor incident occurs during the transport of radioactive materials, the relevant regulations of China shall be observed and the response process shall be initiated when necessary.
Preface, take the necessary emergency measures to protect people, property and the environment.
4.2.2 Emergency procedures should consider other hazardous substances that may arise from the reaction between the contents of the consignment and the environment in the event of an accident.
4.3 Quality Assurance
Design, manufacture, testing, documentation, etc. for all special forms of radioactive materials, low-dispersion radioactive articles and packages,
Use, maintain and inspect, and develop a quality assurance program for transport operations and intermediate storage operations to ensure effective compliance
Standard related requirements. Proof that the design specification has been fully implemented should be submitted to the relevant government department. Manufacturer, consignment
Both the person and the user should facilitate the inspection of the relevant government departments during the manufacturing and use process and confirm with the relevant government departments.
a) all manufacturing methods and materials comply with approved design specifications;
b) All packaging is inspected regularly and repaired and maintained as necessary to maintain good condition, even if it is repeated
All relevant requirements and specifications are still met after use.
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