Application of the Dry Polyfunctional Additives at Radioactive Waste Cementation

2003 ◽  
Author(s):  
Andrey P. Varlakov ◽  
Konstantin M. Efimov ◽  
Valeri N. Tchernonojkine ◽  
Aleksandr S. Barinov ◽  
Olga A. Gorbunova
Keyword(s):  
Radioactive Waste ◽  
Liquid Radioactive Waste ◽  
Aggregation State ◽  
Technological Processes ◽  
Cement Compound ◽  
Liquid Condition ◽  
Solid Radioactive Waste ◽  
The Cost ◽  
Polyfunctional Additive

One of the known methods directed to improving of the technological cementation process, the increasing quality of a cement compound and degree of radioactive waste incorporating into a final product, is use of the various additives to a cement compound. At present there are technological processes where one or two additives in a dry loose or liquid condition in quantity of 1–10% are used. The application of these additives is directed, as a rule, to improving of one or two properties of a cement compound. The magnification of a quantity of the additives and use of them in a different aggregation state is connected with rise in the cost of the technological process. At Institute of Ecology and Technology Problems and Moscow SIA “Radon” the polyfunctional modifying additives representing dry mixtures of original macro- and microadditives to cement have been developed. The polyfunctional additive is introduced by traditional, reliable and inexpensive equipment directly into liquid radioactive waste and intermixed together with the rest of cement. The quantity of additive varies from 5 up to 20% of cement weight. The additives considerably improve all regulated properties of a cement compound (compressive strength, radionuclides leaching, frost resistance, biological resistance, etc.) and allow modifying the required properties (penetrating ability, viability, disintegration, terms of setting, viscosity etc.). Such additives are used both at cementation of solid radioactive waste and cementation of liquid radioactive waste having a complicated chemical composition, for example, containing simultaneously boric acid, sulphates and great quantity of organic compounds. It is important, that the components of the additives did not change the action in a mixture with other ones. In the report the compositions of the polyfunctional additives developed for various waste and technological processes, their properties and results of practical application are represented.

On estimating the cost of processing liquid radioactive waste

1972 ◽  
Vol 32 (6) ◽  
pp. 547-548
Author(s):  
B. S. Pavlov-Verevkin ◽  
M. F. Krasnaya
Keyword(s):  
Radioactive Waste ◽  
Liquid Radioactive Waste ◽  
The Cost

scholarly journals Applying of Seawater Desalination Technologies for the Pre-Evaporation of Liquid Radioactive Waste

2020 ◽  
Vol 18 ◽  
pp. 57-64
Author(s):  
V. P. Kravchenko ◽  
◽  
S. V. Surkov ◽  
Hussam Ghanem ◽  
◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Liquid Radioactive Waste ◽  
Salt Content ◽  
Design Parameters ◽  
Source Water ◽  
Vapor Compression ◽  
Seawater Desalination ◽  
Wide Range ◽  
Desalination Technology ◽  
The Cost

Processing of liquid radioactive waste (LRW) includes evaporation followed by vitrification. Reducing the energy consumption of evaporation of LRW is an urgent task. In the article, an attention is paid to the fact that similar technical and economic problems are solved with the desalination of seawater. It is proposed to use well-developed seawater desalination technologies for preliminary evaporation of LRW. For a detailed analysis, desalination technology with mechanical vapor compression (MVC) was selected. This technology is energy-saving because it implements the heat pump principle. MVC technology is highly efficient, simple, and does not lead to the generation of secondary radioactive waste. A mathematical model of a single-stage desalination plant with MVC has been developed, taking into account that the thermodynamic cycle of this process is open. Since there are no data on the physical properties of LRW in the literature, the properties of sea water were used. The design and operational parameters were optimized in order to reduce the cost of 1 m3 of evaporated water. It has been established that the main design parameters affecting the cost of evaporated water are the degree of vapor compression in the compressor and the heat exchange surface area of the evaporatorcondenser. The influence of these parameters on capital and operating costs is shown. The optimal combinations of these parameters are determined. To ensure the optimal operating mode of the installation, it is necessary to maintain the optimum salt content of boiling brine, which is determined by the rate of consumption of the source water. The optimal values of these parameters are calculated in a wide range of salt content of the source water. It is shown that, at low salinity of the initial LRW, evaporation is advisable to be carried out in a multi-stage installation. As a result of the calculations, it was found that the specific cost of evaporation of liquid radioactive waste with an initial salt concentration of 10% to a salt content of 20% using the desalination technology with mechanical vapor compression is 0.843 USD/m3.

Development of Technology for Cementation of Oil Containing LRW Using Porous Concrete

2007 ◽  
Author(s):  
S. A. Dmitriev ◽  
A. P. Varlakov ◽  
A. V. Germanov ◽  
O. A. Gorbunova ◽  
A. S. Barinov ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
New Technology ◽  
Liquid Radioactive Waste ◽  
Negative Influence ◽  
Cement Matrix ◽  
Porous Concrete ◽  
Cement Compound ◽  
Concrete Matrix

A new technology of oil containing liquid radioactive waste conditioning has been developed at SIA “Radon”. A porous concrete matrix is placed into special containers and impregnated with oil containing liquid radioactive waste. The waste is effectively fixed in the porous cement matrix. The final product has all the regulated properties. The content of oils in the cement compound can be up to 40% wt. The technology excludes negative influence of oils on hydration of cement which usually occurs at co-cementation of oils with salt liquid radioactive waste.

scholarly journals Inclusion of liquid radioactive waste into a cement compound with an additive of multilayer carbon nanotubes

2019 ◽  
Vol 227 ◽  
pp. 052030 ◽  
Author(s):  
Tatiana Kulagina ◽  
Vladimir Kulagin ◽  
Eleonora Nikiforova ◽  
Dmitriy Prikhodov ◽  
Alexander Shimanskiy ◽  
...  
Keyword(s):  
Carbon Nanotubes ◽  
Radioactive Waste ◽  
Liquid Radioactive Waste ◽  
Multilayer Carbon Nanotubes ◽  
Cement Compound

Method of Treatment of Radioactive Silts and Soils

1996 ◽  
Vol 465 ◽  
Author(s):  
A. P. Varlakov ◽  
I. A. Sobolev ◽  
A. S. Barinov ◽  
S. A. Dmitriev ◽  
S. V. Karlin ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Liquid Radioactive Waste ◽  
Current Method ◽  
Initial Mixture ◽  
Toxic Substances ◽  
Chemical Waste ◽  
Wide Range ◽  
Product Volume ◽  
Better Than

ABSTRACTTo solve the problem of silts and soils that are contaminated with radioactive and toxic substances, the following method has been developed at SIA RADON. The material is mixed with limestone and other components, including up to 70 % (mass) of dried residue of liquid radioactive waste. The mixture is heated at 800 to 1000 °C, shredded, and used to form cement. This cementation process may be used to treat radioactive or other chemical waste.The work demonstrated that in the case of silts, for example, the product volume is reduced by a factor of 1.5 to 3 compared to the initial silts volume. A fast hardening, durable product is obtained, the quality of which is not inferior to that obtained by using the traditional binders. For some parameters, e.g., hardening rate and macroelement leaching, the current method is significantly better than the traditional cementation process. It has also been demonstrated that, over a wide range of parameters, when dry residue of liquid radioactive waste is used in the initial mixture, the part of NOxCan be reduced to nitrogen, thereby reducing NOx emissions.

Optimization of heat-liberating batches for ash residue stabilization

1999 ◽  
Vol 556 ◽  
Author(s):  
O. K. Karlina ◽  
G. A. Varlackova ◽  
M. I. Ojovan ◽  
V. M. Tivansky ◽  
S. A. Dmitriev
Keyword(s):  
Radioactive Waste ◽  
Product Quality ◽  
Redox Properties ◽  
Process Safety ◽  
Ash Residue ◽  
Solid Radioactive Waste ◽  
Increasing Process

AbstractOur study is concerned on development of a new stabilisation method of ash residue obtained after incineration of solid radioactive waste by means of heat liberating batches - compositions with redox properties. The results of optimisation of heat-liberating batches with the purpose of increasing process safety and obtained product quality of are discussed.

Advanced Vitreous Wasteforms for Radioactive Salt Cake Waste Immobilisation

MRS Advances ◽  
2020 ◽  
Vol 5 (3-4) ◽  
pp. 121-129
Author(s):  
Vladimir A. Kashcheev ◽  
Nikolay D. Musatov ◽  
Michael I. Ojovan
Keyword(s):  
Radioactive Waste ◽  
Liquid Radioactive Waste ◽  
Synthesis And Characterization ◽  
Cold Crucible ◽  
Leaching Rate ◽  
Salt Cake ◽  
Solid Salt ◽  
Cement Compound

AbstractSalt cake radioactive waste is a remnant solid salt concentrate after deep evaporation of radioactive evaporator concentrate at WWER NPP’s. The traditional cementing of borate-containing liquid radioactive waste, to which the salt cake belongs, leads to a significant increase in the volume of the final product. This work describes borosilicate vitreous wasteforms developed to immobilize radioactive salt cake waste and comprises data on both glass synthesis and characterization. The composition of glass selected for the purpose of immobilisation of the salt cake radioactive waste allows to include up to 40 wt. % of the oxides contained in the salt cake and to reduce the volume of the final product by more than 2 times compared with the cement compound. The batches were melted in a cold crucible melter at 1200 °C. The normalized cesium leaching rate of the vitrified wasteform product was within range 3.0·10-5 – 3.7·10-6 g/(cm2·day).

scholarly journals Liquid Radioactive Solidification Technologies

2019 ◽  
pp. 68-74 ◽  
Author(s):  
V. Svidersky ◽  
V. Glukhovsky ◽  
I. Glukhovsky ◽  
T. Dashkova
Keyword(s):  
Radioactive Waste ◽  
Nuclear Power ◽  
Power Plants ◽  
Liquid Radioactive Waste ◽  
Cement Stone ◽  
Leaching Rate ◽  
Additional Water ◽  
Volumetric Characteristics ◽  
Leaching Parameters ◽  
The Cost

This review provides a brief analysis of familiar and tested technologies of liquid radioactive waste solidification. The technologies of bituminization, vitrification and incorporation of radioactive waste into the polymer matrix are considered. The paper presents the efficiency indices of the conventional cementation technology and sets forth the results of calculating the cost of components for cementing liquid radioactive waste of various concentrations. Besides, there are results of calculating the volumetric characteristics of cement stone for water-cement relations used for cementing liquid radioactive waste. The review includes the results based on the development and implementation of solidification technologies for liquid radioactive waste using contact-hardening binders that form a durable waterproof stone at the time of pressing and do not require additional water for curing. Generated compounds for immobilization of liquid radioactive waste from nuclear power plants are tested to identify their strength characteristics, resistance to irradiation and leaching parameters. The paper covers the calculation of the cost of components for the solidification of liquid radioactive waste of various concentrations. The developed technology of liquid radioactive waste solidification allows obtaining compounds with strength up to 40 MPa. The volume of the final product is increased by 1.8 times, and the leaching rate is in the range of 1.10×10–4…9.5×10–5 kg/m2 per day.

scholarly journals PROMISING AREAS OF TECHNOLOGY FOR THE RESTORATION OF MACHINE PARTS

2020 ◽  
pp. 104-110
Author(s):  
Elena Trukhanska
Keyword(s):  
Economic Effect ◽  
Recovery Process ◽  
Technological Processes ◽  
Constant Friction ◽  
Static And Dynamic Loads ◽  
New Processing ◽  
Quality Of Products ◽  
The One ◽  
The Cost

With prolonged use of machines, wear of parts is accompanied by a decrease in performance indicators, causing a deterioration in the quality of products. The power take-off shaft experiences significant static and dynamic loads. The high wear rate of the power take-off shaft is due to constant friction with the clutch disc, gears, and bearing inner rings. The manufacture of a new power take-off shaft requires significant costs, so the development of new technological processes for repair and restoration is urgent. A promising direction of restoration technology in the organizational plan of deepening the method of group restoration technology is the creation of unified-group equipment for surface restoration. It has been established that most of the parts of remanufactured machines are rejected due to slight wear of the working surfaces, making up no more than 1% of the initial mass of parts. As experience and practice show, on the one hand, it is technically impossible to avoid the repair of agricultural machinery, and on the other, it is economically feasible. After all, most of the worn out parts have a high residual value: during their restoration, 20-30 times less metal and materials are consumed than in the manufacture of new ones. The following problems are considered: the choice of the technological process of restoration, the choice of technological equipment, tools. Restoration of details is a technically justified, economically justified measure. This allows repair shops to reduce downtime of faulty machines, improve the quality of maintenance and repair to positively affect the reliability of the use of machines. To restore the efficiency of worn parts requires 5-8 times less technological operations compared to the manufacture of new ones [1, 2]. Restoration of parts allows you to get a considerable economic effect, as much lower consumption of metal and auxiliary materials, and the cost of the restored part is 60-80% of the cost of new ones. Therefore, to make this recovery process effective, it is necessary to introduce new processing and recovery methods, as well as to improve existing equipment. The production of a new power take-off shaft requires significant costs, and the detection of new technological processes of repair and restoration is relevant.

Parameters Of Technological Processes Reengineering

2020 ◽  
pp. 28-33
Keyword(s):  
Spatial Organization ◽  
Parametric Model ◽  
Practical Significance ◽  
Machine Time ◽  
Time Machine ◽  
Technological Processes ◽  
Technical Capability ◽  
Materials Used ◽  
The Cost ◽  
Qualitative Characteristics

The article is devoted to reengineering of technological processes - a method of their qualitative transformation on an innovative basis, which in turn assumes the availability of tools that make it possible to establish the economic efficiency and technical capability of such transformations of construction production, to identify the effect of their implementation. In this regard, the problem of forming a parametric model of reengineering of construction technological processes, which involves four enlarged groups of indicators that reflect the quantitative and qualitative characteristics of the processes: materials used, working time, machine time, spatial organization, is considered. It is established that parameters can have either an absolute (physical, cost) or relative (point, percentage) expression and also make their own decomposition. The practical significance of the provisions given in the article is determined by the development of methods of technical rationing, which leads to a reduction in the cost and duration of construction.

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