This standard specifies the basic requirements, acceptance criteria and quality assurance for the reception of low- and intermediate-level radioactive solid wastes when they are disposed near the surface. This standard applies to all wastes sent to near-surface disposal sites, mainly wastes generated by nuclear power plants, nuclear fuel cycles and decommissioning of nuclear facilities. Wastes generated in the production and application of radioactive isotopes should also be implemented as a reference. GB 16933-1997 Acceptance criteria for near-surface radioactive waste GB16933-1997 standard download decompression password: www.bzxz.net

GB16933-1997
This standard is mainly based on the International Atomic Energy Agency's 1985 Safety Series Report No. 71 "Criteria for the Acceptance of Radioactive Wastes for Shallow Burial and Cavern Disposal", and is compiled in combination with my country's specific conditions. This standard comprehensively stipulates the basic requirements, acceptance criteria and quality assurance for the acceptance of low- and medium-level radioactive wastes when they are disposed near the surface, thereby providing a unified basis for the acceptance of wastes for my country's near-surface disposal sites. Each specific disposal site should formulate a waste characteristic requirement that is not lower than that specified in this standard in accordance with the provisions of this standard, based on its own site characteristics and disposal repository design requirements, as its own waste acceptance operation document. This standard was proposed by China National Nuclear Corporation. The drafting unit of this standard is: China Institute of Radiation Protection. The main drafter of this standard is: Feng Shengtao.
National Standard of the People's Republic of China
Acceptance criteria
for near surface disposal of radioactive wasteGB16933-1997
This standard specifies the basic requirements, acceptance criteria and quality assurance for the acceptance of low- and intermediate-level solid radioactive waste (hereinafter referred to as "waste") when it is disposed near the surface.
This standard applies to all wastes sent to near surface disposal sites, mainly wastes generated by nuclear power plants, nuclear fuel cycles and decommissioning of nuclear facilities. Wastes generated by the production and application of radioactive isotopes should also be implemented by reference. 2 Referenced standardsbZxz.net
The provisions contained in the following standards constitute the provisions of this standard through reference in this standard. When this standard is published, the versions shown are valid. All standards will be revised, and parties using this standard should explore the possibility of using the latest version of the following standards. GB8703—88 Radiation protection regulations
GB9132-88 Regulations on near-surface disposal of radioactive waste GB11806-89 Regulations on safe transportation of radioactive materials GB12711-91 Safety standard for packaging of low- and intermediate-level radioactive solid waste GB14500-93 Regulations on radioactive waste management GB14569.1-93 Performance requirements for solidified bodies of low- and intermediate-level radioactive waste Cement solidified bodies GB14569.2-93 Performance requirements for solidified bodies of low- and intermediate-level radioactive waste Plastic solidified bodies GB14569.3--1995 Performance requirements for solidified bodies of low- and intermediate-level radioactive waste Asphalt solidified bodies 3 Basic requirements
3.1 The basic principles stipulated in GB8703 must be observed when loading, unloading, transporting, storing and disposing of waste. 3.2 Waste generating units must manage waste in accordance with the provisions of GB14500 so that the waste to be disposed of meets the performance requirements stipulated in the waste acceptance standards of the specific disposal site.
3.3 Waste packaging must meet the requirements of GB12711 and GB11806. 3.4 The formulation of waste acceptance standards for specific disposal sites should be based on the safety assessment of the entire disposal system. 4 Waste acceptance criteria
4.1 Radioactive nuclide content
4.1.1 The specific activity of the waste in the waste packaging should not exceed the management limit specified in GB9132. 4.1.2 The content of fissile materials in the waste packaging should be limited to ensure that nuclear criticality conditions will not be reached. 4.2 Surface radiation level
The maximum radiation level at any point on the outer surface of the waste packaging and the radiation level at any point 1m away must meet the requirements specified in 7.1 of GB12711-91 approved by the State Administration of Technical Supervision on July 30, 1997 and implemented on September 1, 1998. 4.3 Surface contamination
GB16933-1997
Non-fixed contamination of radioactive substances on the surface of waste packaging must meet the requirements specified in 8 of GB12711-91. 4.4 Mechanical stability
4.4.1 The pressure bearing capacity and integrity of waste packaging must meet the requirements specified in 6.2 of GB12711--91. 4.4.2 The mechanical stability of cement and plastic solid bodies must meet the requirements specified in GB14569.1 and GB14569.2. 4.5 Anti-leaching
The anti-leaching of waste solid bodies must meet the requirements specified in 4.3.1 of GB14569.1-93 and GB14569.2-93 and 4.5.1 of GB14569.3-1995. 4.6 Free liquid
4.6.1 There should be no free liquid exudation from the waste solid body. 4.6.2 Other wastes should minimize or eliminate free liquid exudation. 4.6.3 The volume of free liquid in the waste container should be less than 1% of the volume of solid waste. 4.7 Chemical composition
4.7.1 The content of chelating agents and complexing agents in the waste must be less than 1% of the weight of the waste. 4.7.2 The content of the following components in the waste must be controlled to avoid harmful chemical reactions: a) oxidizing substances;
b) corrosive substances;
c) water.
4.7.3 The waste must not contain the following substances: a)
self-igniting substances;
b) explosive substances;
c) organic flammable substances with low boiling points or low flash points close to ambient temperature. 4.8 Thermal and radiation stability
The waste must have sufficient thermal stability and radiation resistance. The radiation resistance of cement and plastic solidification bodies must meet the requirements specified in 4.5 of GB14569.1-93 and GB14569.2--93. The radiation resistance of asphalt solidification bodies must meet the requirements specified in 4.7 of GB14569.3-1995. 4.9 Fire resistance
4.9.1 The fire resistance of plastic and asphalt solidification bodies must meet the requirements specified in 4.6 of GB14569.2--93 and GB14569.3-1995.
4.9.2 Combustible compressed and reduced volume waste must be packaged to greatly reduce the possibility of fire. 4.10 Microbial damage resistance
4.10.1 The waste body must not contain untreated easily degradable animal bodies and other organisms. 4.10.2 The content of organic waste that is easily destructed by microorganisms in the waste body should be limited. 4.11 Gas Generation
Gases generated in waste packaging due to radiolysis, radioactive decay, chemical reactions between waste and solidified materials, and decomposition of organic matter should not lead to damage to the efficiency of the disposal system. 4.12 Packaging Containers
The design and manufacture of waste packaging containers must meet the requirements of GB11806-897 and GB12711-916. 4.12.1 Waste packaging containers can be made of carbon steel, stainless steel, cast iron, concrete, polymer impregnated concrete, or fiberglass. For materials prone to rust, anti-corrosion paint must be applied.
4.12.2 National standard containers should be used for waste packaging. 4.12.3 For waste packaging exceeding a certain weight, its packaging container must be equipped with a strong slot or lifting structure766
part that is convenient for safe loading and unloading.
4.13 Filling volume of packaging container
GB16933—1997
The filling volume of packaging container must be greater than 85% (by volume). 4.14 Marking, numbering and labeling
4.14.1 The outer surface of waste packaging must bear the marking and numbering specified in 9.1 and 9.2 of GB12711-91. 4.14.2 The content and technical requirements of the waste packaging label must be consistent with the provisions of 9.2 and 9.3 of GB12711-91. 5 Quality assurance
5.1 Quality assurance program
The quality assurance of waste reception is an integral part of the comprehensive quality assurance of the entire management system from waste generation, treatment, packaging, storage, transportation to disposal. Both waste generating units and disposal sites must formulate a quality assurance program to ensure that waste packaging meets the basic requirements and criteria for waste reception specified in this standard.
5.2 Quality Assurance Organization
Waste generating units and disposal sites must establish their own quality assurance organizations and strictly implement the provisions of Article 10 of GB9132-88. 5.3 Acceptance and sampling inspection
5.3.1 During the waste acceptance process, the disposal site must check the following items in addition to checking the necessary documents: a) delivery note and delivery label;
b) waste packaging mark;
c) waste packaging surface dose rate and surface contamination; d) whether the waste packaging meets the safety packaging requirements and whether it is damaged during transportation. 5.3.2 The competent authority or disposal site operator may authorize a qualified department or unit to conduct destructive or non-destructive random inspections on waste packaging. The random inspection items may include the following items: a) total β- and total α radioactivity; b) main radionuclides and their specific activities; c) surface dose rate, d) surface contamination; chemical composition of the original waste; f) properties of the solidification matrix; g) quality of the waste container; h) ratio of waste/solidification matrix/water/additives; mixing uniformity; j) weight, main nuclide diffusion rate; 1) moisture content; m) curing of the solidification body; n) thermal properties; o) stackability.
5.4 Data and Document Management
5.4.1 All data, reports and documents related to waste reception must be collected and summarized and entered into the computer network system to track the flow of waste through computer control and provide all necessary data for waste quality assurance. 5.4.2 All data, reports and documents related to waste reception must be properly managed and stored in two places in the form of original and duplicate copies. 767
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