GB/T 4960.8-1996 Terminology of Nuclear Science and Technology Radioactive Waste Management
Some standard content:
ICS27.120.01
National Standard of the People's Republic of China
GB/T4960.8—1996
Glossary of term:nuclear science and technology
Radioactive waste management
Issued on 1996-06-17
Implemented on 1997-07-01
State Administration of Technical Supervision
Subject content and scope of application
Cited standards
Basic terms
Waste classification
Waste pretreatment
Waste treatment
Waste preparation
Waste transportation and storage…
Waste disposal
Uranium (needle) mining and metallurgy waste management
Safety assessment
Chinese index (supplement)
Appendix A
Appendix B English index (supplement)
National Standard of the People's Republic of China
Nuclear science and technology terms
Radioactive waste management
Glossary of term: nuclear science and technology
Radioactive waste management1 Subject content and scope of application
This standard specifies the basic terms and definitions of radioactive waste management. GB/T4960.8—1996
Replaces GB4960--85
This standard applies to international and domestic technical exchanges, trade exchanges and the compilation of standards, books, periodicals or documents in the field of radioactive waste management.
2 Reference standards
GB11806 Regulations on the safe transportation of radioactive materials. 3 Basic terms
3.1 Radioactive waste (radwaste): nuclear wastenuclearwaste
Waste containing or contaminated with radionuclides, whose concentration or specific activity is greater than the clean clearance level determined by the regulatory agency, and is not expected to be reused. (This definition is entirely from the management point of view. Materials with radioactive concentrations equal to or lower than the clean clearance level are still radioactive from a physical point of view, but their radioactive hazards can be ignored.) 3.2 Waste generation wasteearisings
The amount of waste generated by various stages of the nuclear fuel cycle, reactors and the production and utilization of radioactive isotopes. 3.3 Waste management wastemanagement
All administrative and technical activities including the pretreatment, treatment, preparation, transportation, storage and disposal of waste. Waste pretreatment wasteretreatment
One or all operations before waste treatment. For example: collection;
Separation and (or) diversion;
Chemical conditioning;
Decontamination.
3.5 Waste treatment
wastetreatment
Operations that change the characteristics of waste for safety and (or economic purposes). The basic tasks of treatment are: a. Volume reduction;
Remove radionuclides from waste,
Approved by the State Administration of Technical Supervision on June 17, 1996 and implemented on July 1, 1997
c. Change composition.
GB/T4960.8—1996
After treatment, the waste may be fixed or not fixed to obtain a suitable waste body. 3.6 Waste conditioning operations to form a package suitable for loading and unloading, transportation, storage and (or) disposal. Conditioning may include converting the waste into a solid body, encapsulating it in a container, and providing outer packaging when necessary. 3.7 Waste disposal wastedisposal
Place the waste in an approved, special facility (such as a near-surface or geological disposal repository) and do not retrieve it. Disposal may also include the approved direct discharge of effluents into the environment and subsequent dispersion. 3.8 Waste minimization is the principle of reducing the amount and activity of waste to the minimum that can be reasonably achieved. Minimization should be carried out throughout the entire process from the design of nuclear facilities to the end of decommissioning. Minimization includes reducing source items, recycling and reuse, and the treatment of secondary waste and primary waste. 3.9 The principle of being as low as reasonably achievable, the ALARA principle, in the design, operation and related practices of nuclear facilities, should ensure that the exposure is as low as reasonably achievable under technical, economic and social factors. ALARA is the abbreviation of "as low as reasonably achievable". 3.10 Source term sourceterm
A description of the radiation or radioactive material actually or potentially released by a given radiation source, such as the composition, initial amount, release rate and release pattern of the released material.
3.11 Waste inventory waste inventory
A detailed itemized record maintained by the operating unit in accordance with regulations. The waste inventory may contain data such as the number of entities (number of waste packages), activity of the waste, content of radionuclides and (or) characteristics of the waste solid body. 3.12 Specific (chemical) state specification The chemical state of radionuclides under specific conditions (pH, Eh, ligands, ion strength)
3.13 Effluent; effluent
Waste gas or liquid discharged into the environment.
3.14 Effluent control level; discharge limit
The management limit of radioactive concentration and total amount specified to control the pollution of the environment by radionuclides in the effluent. 3.15 Routine discharge is the planned and controlled release of radioactive effluent into the environment. Such release should comply with all restrictions established by the relevant regulatory agencies.
3.16 Dispersion
Gas or liquid The process by which body effluent is transported in the air or water, through diffusion and mixing, and eventually reaches dilution. 3.17 Clearance level: A group of numerical values set by the regulatory agency, expressed in radioactive concentration and (or) total activity. Any radiation source whose value is equal to or lower than this level can be released from the nuclear management and control system. 3.18 Exemption; exemption is made by the regulatory agency. Because some radiation sources have such low radioactive hazards that they can be exempted from the control of the nuclear management system, that is, they can not enter the management and control system (no control is imposed), or be released from the management and control system (cancel control). In both cases, the radioactive hazards associated with these radiation sources are small enough to be ignored. 3.19 Decommissioning Actions taken to take full account of the health and safety of workers and the public and environmental protection after a nuclear facility has reached the end of its life or ceased to be in service for other reasons. The ultimate goal of decommissioning is to achieve unrestricted opening and use of the site, which may take several years to hundreds of years. According to legal and administrative requirements, if a nuclear facility or its remaining part is merged with a new or existing nuclear facility, or even if the site is still under the control of a management agency or administrative agency, the nuclear facility may be considered to have been decommissioned. This definition does not apply to the closure of uranium mining and hydrometallurgical plants and the closure of radioactive waste disposal sites. 3.20 Remediation activity The environment of uranium mines, hydrometallurgical plants and other nuclear facilities is treated through a series of measures to eliminate environmental hazards. 3.21 Transmutation
Transmutation is a method of converting long-lived radioactive nuclides into short-lived or stable nuclides. This technology is under research. 3.22 Partitioning &.Transmutation technology (P&T Technology) separates the steel-based elements, long-lived fission products and long-lived activation products in high-level radioactive waste into groups, makes them into fuel elements and sends them to the reactor for combustion or makes them into targets and puts them into accelerators for bombardment, and transforms them into short-lived nuclides or even stable elements, reducing the burden and long-term danger of geological disposal of high-level radioactive waste, and may make better use of natural resources and reduce the demand for uranium. 4 Waste classification
4.1 Radioactive gaseous waste; radioactive gaseous waste radioactive gaseous waste contains airborne materials and (or) gas streams of radioactive nuclides. Depending on the level of radioactivity, gaseous waste is either discharged after treatment or left for further treatment and disposal.
4.2 Radioactive liquid waste; radioactive liquid waste radioactive waste in liquid form, which may contain dissolved, colloidal or dispersed solids. Because liquids are fluid and dispersed, they usually need to be solidified.
4.3 Radioactive solid waste Radioactive solid waste in solid form, including labor protection products and tools and equipment that are contaminated by radioactivity and are treated as waste, as well as solidified bodies transformed from radioactive waste liquid.
4.4 Low-level waste (LLW) The content or concentration of radioactive nuclides in this type of waste is low, and shielding is usually not required during normal operation and transportation. 4.5 Intermediate level waste (ILW) Although the content or concentration of radioactive nuclides and the heat release in this type of waste are lower than those in high-level waste, appropriate protective measures need to be taken during normal operation and transportation.
4.6 High-level waste (HLW) The content or concentration of radioactive nuclides in this type of waste is high, and the heat release is large, so special protection is required during operation and transportation. It mainly includes high-level waste liquid and its solidified bodies produced by spent fuel reprocessing, spent fuel to be directly disposed of, and other wastes of corresponding radioactive levels. 4.7 Short-lived waste short-lived waste Radioactive waste containing radionuclides that will decay to insignificant levels from a radiation point of view within the specified control period. The half-life of radionuclides in short-lived waste is usually shorter than or equal to 30 years. 4.8 Long-lived waste long-lived waste
Radioactive waste containing long-lived radionuclides, whose quantity or concentration has sufficiently high radioactivity to require long-term isolation from the biosphere. "Long-lived nuclides" refer to nuclides with a half-life greater than 30 years. 4.9 Alpha bearing waste
Waste containing one or more alpha-ray emitting nuclides, whose total alpha radioactivity activity exceeds the limit set by the regulatory agency. 4.10 Transuranic waste (TRU waste) Waste containing nuclides with atomic numbers greater than 92, whose content and/or concentration exceeds the limit set by the regulatory agency. Simulated waste Simulated waste
Imitation of a certain type of waste, whose composition, physical properties and chemical properties are as close as possible to the real radioactive waste, sometimes containing tracer 3
amounts of radionuclides.
4.12 Heat generating waste heat generating waste GB/T4960.8-1996
Waste whose decay heat released by the radionuclides contained in it significantly increases the temperature of itself and the surrounding environment. 4.13 Combustible waste combustible waste, burnable waste radioactive waste that can be burned, such as contaminated protective clothing, hand towels, mops, etc. 4.14 Compressible waste compressible waste solid waste that can be reduced in volume (volume reduction) by pressurization. 4, 15 Raw waste Raw waste
Primary waste Primary waste
Waste that retains the state and properties when it was produced - unprocessed waste. 4.16 Secondary waste; secondary waste secondarywaste Waste produced as a by-product in the waste treatment process. 4.17 Activated waste activatedwaste
Radioactive waste formed by the activation of nuclear particles or rays. 4.18 Tritiatedwaste, tritium-bearingwaste Waste containing radionuclide atmosphere, whose concentration or specific activity exceeds the clean clearance level specified by the regulatory agency. 4.19 Detergent waste detergentwaste Liquid radioactive waste containing detergent, soap or similar organic matter, usually with a low radioactivity concentration. Claddingwaste
Radioactive waste composed of broken cladding, top cover, spacer grid and other components in the spent fuel assembly, which is produced from the reprocessing of spent fuel.
4.21 Control rod waste controlrodwaste Abandoned used reactor control rods and their accessories. 4.22 Defense waste defensewaste
Radioactive waste generated by the development and utilization of nuclear energy and nuclear technology for military purposes. 4.23 Commercial waste commercialwaste Radioactive waste generated by the development and utilization of nuclear energy and nuclear technology for civilian use. Usually refers to waste generated by nuclear power plants and isotope production and utilization.
4.24 Non-nuclear industrial waste non-nuclearindustrywaste Expected useless materials generated by the use and processing of materials containing natural radionuclides (such as phosphate ore). It is different from the waste generated by the nuclear fuel cycle.
4.25 Exempt waste; exempt waste exemptwaste Waste exempted from control by the regulatory agency within the scope of radioactive waste management because its related radioactive hazards can be ignored. 4.26 Mixed waste mixedwaste Radioactive waste containing non-radioactive poisons and hazardous substances that have adverse effects on the environment. The treatment, processing and disposal of this waste must take into account both its chemical composition and radioactive components. Wet waste wetwaste
Usually refers to waste with water, such as: evaporation residue, mud, waste resin, etc. 4.28 Dry waste usually refers to waste without water, such as contaminated labor protection products and tools and equipment. 4.29 Spent radioactive sources are radioactive sources that have been discarded due to expiration of their service life or other reasons. These waste radioactive sources may still have a relatively high activity and must be properly disposed of.
5 Waste pretreatment
GB/T4960.8—1996
5.1 Waste acceptance criteria waste acceptance criteria are waste acceptance requirements and standards formulated to facilitate the transportation, storage and disposal of waste. 5.2 Waste segregation waste segregation waste into radioactive waste or exempt waste or classify radioactive waste according to its radioactive characteristics or physical and chemical characteristics for waste treatment or processing.
5.3 Sorting technique
The technology of separating non-radioactive materials and recyclable materials mixed in waste on the sorting table (manually or automatically) by using radiation monitoring equipment, or separating combustible and non-combustible wastes, compactable and non-compactable wastes, so as to facilitate their separate treatment later. 5.4 Waste (manual) handling wastehandling Manual operation of waste (such as sorting, transportation) or packaging of waste. 5.5 Waste conditioning wastejustment
Modulation of the waste system (such as pH adjustment, etc.) to meet the needs of further treatment. 5.6 Contamination
The presence of radioactive substances in materials or on the surface of objects, or in the human body and other places where the presence of radioactive substances is undesirable or harmful. 5.7 Decontamination
The process of removing or reducing radioactive contamination by physical and (or) chemical methods. 5.8 Chemical decontamination Chemical decontamination The process of removing or reducing surface contamination by chemical methods. 5.9 Decontamination factor: the ratio of the radioactivity level before and after decontamination by pollutants; 5.10 Decontamination index: the common logarithm of the decontamination factor.
5.11 Hotspot
A part of a radioactive contaminated area where the contamination level is significantly higher than the average. 6 Waste treatment
6.1 Off-gas
Gaseous effluent generated from the process of the facility. For example, dissolution, evaporation, incineration, glass solidification, asphalt solidification, and cement solidification may all produce off-gas. The off-gas may contain water vapor, acid gas, radioactive aerosols, radioactive gases and other chemical components. 6.2 Off-gas treatment
Remove radionuclides and chemical pollutants from the off-gas before releasing it into the atmosphere under controlled conditions. 6.3 Off-gas cleaning system A combined device for off-gas purification and treatment. Usually includes a scrubber, an adsorption column, and a filter. 6.4 High efficiency particulate air filter high efficiency particulate air filter (HEPA filter); absolute filter absolute filter
A high-efficiency dry filter used to remove submicron or slightly larger particles in gaseous effluents. For particles with a particle size of 0.3um, the filtration efficiency is not less than 99.97%. 6.5 Iodine adsorption system A device used to remove airborne radioactive iodine produced during reactor operation, spent fuel reprocessing and isotope production. Also known as an iodine filter.
6.6 Candle filter
GB/T4960.8—1996
A tubular filter made of sintered metal or ceramics processed by powder metallurgy. 6.7 Filter cartridge
A porous filter medium component in the filter. 6.8 Filtering efficiency The ability of the filter to retain dust or radioactive substances. Its value is the ratio of the difference in dust or radioactive concentration in the gas before and after filtration to the original dust or radioactive concentration before filtration.
6.9 Recombiner
A device that can controllably carry out hydrogen-oxygen recombination reaction by catalysis or electric heating. 6.10 Defog, demist
Remove mist entrained in gas or steam. There are dry method, wet method, adsorption method, electrostatic method, etc. 6.11 Entrainment
The phenomenon that tiny liquid droplets in the gas-liquid system escape with the gas. 6.12 Cryogenic adsorption system A device that uses adsorbents to adsorb certain radioactive gas components in the gas at low temperature to retain them. 6.13 Pressurized gas storage system A storage system operating at a pressure greater than 0.15MPa, suitable for the storage of radioactive waste gas before discharge or reuse. 6.14 Radioactive gas decay tank A container that collects or stores gas containing short half-life radioactive nuclides under pressure. Its purpose is to retain radioactive nuclides until they decay to a lower level.
6.15 Delay system
A device that uses adsorbents to retain radionuclides so that the radioactivity level is reduced through decay. 6.16 Radioactive aerosol Radioactive aerosol A dispersion of tiny solid particles or liquid droplets of radionuclides in the air or other gases. 6.17 Clean liquid waste;
High purity liquid waste; High purity liquid waste Radioactive liquid waste with low conductivity (usually <5×10-s/m) and containing only a moderate amount of insoluble solid particles (usually <20×10-8).
6.18 Low purity liquid waste: low purity liquid waste dirty liquid waste
Radioactive liquid waste with medium conductivity (usually 5×10-8~20×10-Bs/m) and containing medium amount of insoluble solid particles (usually 20×10-8～500×10-8).
6.19 Regeneration liquid waste generally refers to the radioactive liquid waste produced in the regeneration process of ion exchange resin. 6.20 Evaporation residue, evaporator bottom, residues The concentrate remaining after heating the waste liquid to evaporate most of the solvent. 6.27 Laundry wastewater laundry wastewater
Wastewater produced in the operation of radioactive work clothes laundry. 6.22 Decladding liquid waste Radioactive liquid waste produced by chemical dissolution of spent fuel element cladding. 6.23 Processing wasteprocessingwaste
Radioactive wastes such as ion exchange resin regeneration liquid, equipment cleaning wastewater and unreusable boric acid generated by nuclear power plant systems. 6.24 Filtration
GB/T 4960.8-1996
The process of separating solids from solid-liquid or solid-gas mixtures with the help of porous media such as filter paper, cloth or glass fiber. 6.25 Dewatering
The process of removing water from materials (such as radioactive precipitates, mud, waste resin, etc.) by centrifugation, filtration, freeze-thaw or other solid-liquid separation techniques.
6.26 Denitration
The process of converting (reducing) nitrate (NO) into volatile nitrogen oxides by heating, chemical or electrolytic methods. Spent fuel reprocessing is usually carried out in a nitric acid medium, so denitrification is an important step in the waste treatment process. Demineralizing
The process of removing salt from water or radioactive waste liquid. 6.28 Reverse osmosis
The process in which the solvent in a solution moves through a semipermeable membrane to a pure solvent or a low-concentration solution on the low-pressure side under pressure, thereby separating the solvent from the solution.
6.29 Electrodialysis
The process of using the ion-selective permeability of an ion exchange membrane to directional migrate positive and negative ions in radioactive waste liquid under the action of an electric field, thereby achieving purification.
6.30 Emulsion
A uniform, highly dispersed system formed by two immiscible liquid phases (e.g., oil and water). 6.31 Suspension liquid
A liquid dispersion system composed of insoluble solid particles dispersed in a liquid. 6.32 Suspended crud
Suspended insoluble particulate matter contained in a liquid stream. 6.33 Settling
The process of separating solid particles in a non-uniform system (liquid-solid, gas-solid) by the force of gravity. 6.34
Precipitation
A chemical method for treating radioactive waste liquid. Radionuclides are removed from liquid by combining or carrying insoluble products produced by chemical reactions in the liquid.
6.35 Coprecipitation
The simultaneous precipitation of two or more substances. It is a chemical treatment method that transfers radionuclides from the liquid phase to insoluble precipitates.
6.36 Flocculation
The process of removing fine solid particles (usually colloidal particles) from waste liquid by neutralizing charges and causing neutral particles to agglomerate and precipitate. Pre-coated filter pre-coated filter 6.37
A device that pre-coates a layer of solid material on the surface of the filter medium to improve the efficiency of separating solid particles from liquid-solid mixtures. 6.38 Superfine filter A device that uses microporous filter material or filter membrane to purify waste liquid under the action of external force. 6.39 Magnetic filter A filtering device that uses magnetic force to capture magnetic substances in the liquid flow. 6.40 Slurry waste Slurry waste produced during the flocculation and sedimentation process. 6.41 Sludge Sludge Suspended particles separated from waste liquid by sedimentation or other solid-liquid separation methods. 6.42 Freeze-thaw Freeze-thaw A slurry dewatering treatment technology that uses the freeze-thaw process to destroy the colloidal structure to facilitate solid-liquid separation. 7 GB/T4960.8—1996
b. A test method for evaluating the performance of a solidified body by simulating the change of climatic conditions and testing the ability of the solidified body to withstand climate change. 6.43 Forced circulation evaporator An evaporator that circulates the liquid in the circulation pipe through the circulation of a pump. 6.44 Scraper thin film evaporator A vertical evaporation device that uses the centrifugal force of rotating blades to spread the waste liquid on the heated cylinder wall into a thin film, so that the water evaporates quickly and the concentrate is discharged from the lower end of the cylinder. 6.45 Heat pump heat pump
A compressor that passes low calorific value steam through a compressor to increase the pressure and heat to become useful heat energy is called a heat pump. 6.46 Compression evaporator A device that uses a heat pump to extract the secondary steam of the boiling liquid and compress it to increase its temperature, and then transfers its latent heat to the cooler boiling liquid for evaporation.
6.47 Steam generator blowdown is the operation of draining liquid from the secondary side of the steam generator to maintain the appropriate chemical content in the coolant. Concentration method
A method of concentrating radioactive waste liquid to reduce its volume, such as evaporation, precipitation and ion exchange. 6.49 Sorption
Refers to the phenomenon that occurs in the pores or on the surface of solids. It includes two mechanisms: absorption and adsorption. The absorption reaction occurs in the pores of solids. The absorption capacity of solids is proportional to the pore volume; the adsorption reaction occurs on the surface of solids, and its capacity depends on the surface area of the solid.
6.50 Adsorption
The phenomenon that ions, molecules or particles adhere to the surface of solids in contact with them. Adsorption process
A method of treating liquids or gases with porous solid adsorbents so that one or several components contained in them are adsorbed on their surface to achieve separation and purification.
6.52 Adsorbent
Material with the ability to adsorb gases or solutes. 6.53
Concentrate
Concentrate
Material concentrated from a dilute stream by some method, such as distillation residue. 6.54 Solvent cleanup
Treatment of used solvents to remove their degradation products, etc., in order to restore extraction performance, reduce radioactivity levels and (or) achieve purification purposes.
6.55 Ion exchange process Ion exchange process Exchange of certain cations or anions in the solution with ions of similar charge on the active groups of the ion exchanger to achieve separation and purification purposes. It is a commonly used method for treating radioactive waste liquid. 6.56 Inorganic ion exchanger Natural or synthetic inorganic substances with ion exchange properties. 6.57 Spent resin Spent resin
Used ion exchange resin containing radionuclides that is no longer reused. 6.58 Diatomaceous earth
Porous and lightweight rock formed by the shells of diatoms and animals. Vermiculite
Hydrated silicate minerals of magnesium, calcium, iron, etc., (Mg, Fe, AI) (AI, Si).O(OH), ·4H,O, in the form of flakes, with a certain ion exchange capacity for some metal ions (such as strontium, cadmium, etc.), and can be used to treat low-level radioactive waste liquid. 8
6.60 Zeolite
GB/T4960.8—1996
A type of hydrated aluminum silicate minerals of calcium, sodium, strontium, and strontium, with a high ion exchange capacity, and can be used to treat radioactive waste. 6.61 Filter aid
Material added to the solution or pre-coated on the filter medium to help separate substances that are difficult to filter. 6.62 Anti-foaming agent anti-foaming agent soluble compound that inhibits or reduces the production of foam. 6.63 Coagulant aid additive that increases the effect and speed of coagulation. 6.64 Anti-coagulant substances that prevent coagulation.
6.65 Incineration technology that uses specially designed incinerators to burn combustible waste. 6.66 Controlled-air incineration control of air volume and combustion temperature to achieve complete combustion of solid waste. 6.67 excess-air incineration the simplest form of incineration. Incineration is carried out under excess air. 6.68 Pyrolysis decomposition of substances caused by heat.
6.69 Pyrolysis incineration The organic components of the waste are first cracked into volatile gases in an oxygen-deficient reaction chamber and then enter a combustion chamber with excess air for complete combustion. 6.70 Slagging incineration Combustible waste and a small amount of non-combustible waste are mixed together and burned at high temperature to produce slag that can be directly disposed of. 6.71
Wet oxidation
A treatment method that uses concentrated sulfuric acid plus an oxidant (such as concentrated nitric acid) or hydrogen peroxide plus a catalyst to oxidatively decompose organic waste in an aqueous phase under heating conditions.
6.72 Acid digestion
A method of chemically decomposing a substance into simpler components (usually soluble or gaseous) using an oxidizing acid in waste treatment to facilitate further waste treatment. For example, organic matter contaminated with alpha nuclides can be digested with acids to achieve the purpose of concentrating radionuclides.
6.73 Fluidized bed
Technology in which solid particles are fluidized in a furnace bed by means of an upwardly moving air stream to promote chemical and physical changes. 6.74
Fluidized-bed incineration is the incineration of waste using a fluidized process.
6.75 Compaction
Technology in which the volume of waste is reduced by external pressure. a.
Compacting the soil covering a near-surface disposal facility to reduce its permeability. b.
6.76 Supercompactor-A high-pressure (greater than 9.8×10°N) compression device. It can fully reduce the volume of solid waste. 6.77
Compaction in drum
The process of compacting waste in a waste drum. Usually, after one compaction, waste is added and compacted again until it is filled to a certain level. Drum compression drumcrushing
The waste is compressed into a smaller volume together with the packaging drum, and then several compacted "cakes" are placed in a larger drum or container. 6.79 Volume reduction volume reduction
The process of reducing the volume of radioactive waste.
GB/T4960.8—1996
6.80 Volume reduction factor volume ratio of radioactive waste before and after volume reduction. Microbial treatment microbial treatment 6.81
Methods of treating radioactive waste using the metabolic effects of microorganisms (such as degrading radioactive waste or enriching radionuclides in solutions, etc.).
6.82 Biodegradation biodegradation
Decomposition or other destruction of waste bodies caused by the action of bacteria or other organisms. 7 Waste conditioning
7.1 SolidificationwwW.bzxz.Net
A method of converting gas, liquid or liquid-like substances into solids, usually forming an object that is easy to process (handle and unload) and has stable physical properties and is not easy to disperse. Cement solidification, asphalt solidification, and glass solidification are some typical methods of solidifying liquid wastes.
7.2 Immobilization
Convert waste into a waste body with low possibility of migration or dispersion of radionuclides during handling, transportation, storage and disposal through solidification, burial or containment.
7.3 embedding
Filling solid waste (such as metal parts) with a base material (such as cement slurry, molten asphalt) to form a waste body. 7.4 encapsulation
Mixing dispersed materials (such as ash, powder, solid waste) with the base material to form a whole waste body. Fixation (of radionuclides) 7.5
Fixing radionuclides on a solid surface by physical means to prevent them from dispersing. Usually refers to applying paint or similar materials on the contaminated surface to prevent the radionuclides from becoming aerosols or being transferred due to some contact. 7.6 waste form
Solid material with a certain physical and chemical form formed by processing and (or) preparation before packaging. The waste body is part of the waste package.
7.7 solidified radioactive waste solidified radioactive waste solid waste formed after the transformation of liquid (or liquid-like) waste. This conversion can be accomplished by calcination, drying or by incorporation into a matrix such as glass, cement, asphalt or plastic. (See also conditioning, fixation, solidification.) 7.8 in-drum solidification The process of adding waste and solidifying agent to a drum and stirring and mixing them to solidify. 7.9 out-drum solidification The process of mixing the waste and solidifying agent outside the drum and then injecting them into the drum for solidification. 7.10 in situs solidification The solidification and disposal of wastes directly at their place of generation or storage. 7.11 monolithic product A solidified body in complete, massive form.
7.12 homogeneous product A solidified body in which the waste components are evenly distributed.
7.13 matrix
Non-radioactive materials used to solidify or fix radioactive wastes, such as cement, asphalt, glass, etc. 7.14 cementation, cements solidification10
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