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.

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.

The Mochovce Final Treatment Center for Liquid Radioactive Waste Introduced to Active Trial Operation

2007 ◽  
Author(s):  
T. Krajc ◽  
M. Stubna ◽  
K. Kravarik ◽  
M. Zatkulak ◽  
M. Slezak ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Liquid Radioactive Waste ◽  
Cement Grout ◽  
Cement Matrix ◽  
Waste Products ◽  
Final Disposal ◽  
Final Treatment ◽  
Treatment Centre ◽  
Steel Drums ◽  
Spent Resin

The Final Treatment Centre (FTC) for Mochovce Nuclear Power Plant (NPP) have been designed for treatment and final conditioning of radioactive liquid and wet waste produced by named NPP equipped with Russian VVER-440 type of reactors. Treated wastes comprise radioactive concentrates, spent resin and sludge. VUJE Inc. as an experienced company in field of treatment of radioactive waste in Slovakia has been chosen as main contractor for technological part of FTC. During the realisation of project the future operator of Centre required the contractor to solve the treatment of wastes produced in the process of NPP A-1 decommissioning. On the basis of this requirement the project was modified in order to enable manipulations with waste products from A-1 NPP transported to Centre in steel drums. The initial project was prepared in 2003. The design and manufacture of main components were performed in 2004 and 2005. FTC civil works started in August 2004. Initial non-radioactive testing of the system parts were carried out from April to September 2006, then the tests of systems started with model concentrates and non-radioactive resins. After the processes evaluation the radioactive test performed from February 2007. A one-year trial operation of facility is planned for completion during 2007 and 2008. The company JAVYS, Inc. is responsible for radioactive waste and spent fuel treatment in the Slovak republic and will operate the FTC during trial operation and after its completion. This Company has also significant experience with operation of Jaslovske Bohunice Treatment Centre. The overall capacity of the FTC is 820 m3/year of concentrates and 40 m3/year of spent resin and sludge. Bituminization and cementation were provided as main technologies for treatment of these wastes. Treatment of concentrate is performed by bituminization on Thin Film Evaporator with rotating wiping blades. Spent resin and sludge are decanted, dried and mixed with bitumen in blade homogeniser. The bitumen product is discharged into 200dm3 steel drums. Drums with bitumen product or drums originated from A-1 NPP are loaded into Fibre Reinforced Concrete containers (FRC) and grouted with cement. Cement grout is prepared from the mixture of cement, additive and radioactive over-concentrate. By formulating the cement grout with evaporator concentrates the maximum radioactivity is fixed in cement matrix and volume of final waste product is minimized. A batch mixer with rotating blades is used to produce the cement grout. The grouted FRC containers are stored in the expedition hall and after 28 days of curing are transported to final disposal. After the start of routine operation, the FTC provides treatment for all liquid and wet LLW produced from the operation of the Mochovce NPP. The final product of the FTC is a FRC loaded with bitumen product in drums and filled with radioactive cement product. This container meets all limits for final disposal in the National Radioactive Waste Repository at Mochovce. This paper introducing the main parts of FTC and describes the technological procedures including the basic technological parameters for both used technologies, their working capacity and the overall waste flow. The evaluation of experience gained in the phases of Centre construction and commissioning and partially trial operation as well is a part of this paper (Evaluation of completion works process and time schedule, testing of systems using model media, radioactive testing and trial operation).

Cementation of Problem LRW Using Porous Concrete

2009 ◽  
Author(s):  
Andrey P. Varlakov ◽  
Alexandr V. Germanov ◽  
Sergey A. Dmitriev ◽  
Alexandr S. Barinov ◽  
Artur E. Arustamov
Keyword(s):  
Radiation Safety ◽  
Pore Space ◽  
Organic Liquid ◽  
Age Hardening ◽  
Cement Matrix ◽  
Liquid Radioactive Wastes ◽  
Porous Concrete ◽  
Surface Active ◽  
Concrete Matrix ◽  
Active Substances

Problem wastes are defined as those wastes which are solidified with difficulty, have poor volumetric efficiencies or produce an unsatisfactory product, demands much of radiation safety of technological process. These wastes are organic liquid (oil, solvents, extractants, scintillation cocktail and others), high containing surface-active substances, subacid aqueous saline and high containing alpha nuclides LRW. The technology consists in as follows. First of all, porous concrete is prepared by a special mixer and placed into a container. The container is the standard drum 100 or 200 l. At the age-hardening of concrete not less than 28 days, when main hydration processes are finished, problem LRW is pumped into the pore space of the porous concrete matrix through previously positioned the special feed tube. The hardened porous concrete matrix is impregnated with problem liquid radioactive wastes which penetrate into the pore space. Depending on kind of LRW contents of waste in the final product has made 50–65% vol. The final conditioning product has meet requirements. LRW is fixed very reliable inside pores of the cement matrix.

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

Application of Metallography for the Slovak Nuclear Power Plants

2014 ◽  
Vol 782 ◽  
pp. 186-190
Author(s):  
Michal Kapusňák ◽  
Ľudovít Kupča
Keyword(s):  
Radioactive Waste ◽  
Nuclear Power ◽  
Power Plants ◽  
Liquid Radioactive Waste ◽  
Cement Matrix ◽  
Surveillance Program ◽  
General View ◽  
Corrosion Stability ◽  
Long Term Storage ◽  
Long Run

The austenitic cladding of liquid radioactive waste underground storage tanks was recently required to be under continuous corrosion surveillance with aim to monitor its corrosion stability until all radioactive waste will be processed and safely stored. Tanks are intended primarily to be used for long-term storage of radioactive waste water solutions and nascent sediments. Tanks are components of technology designed for post-processing of radioactive sediments by means of cement matrix fixation. This paper is dealing with an example of metallografical methods focused on corrosion processes monitoring using the special surveillance program. The brief information is presented for the preparation of specific long-run corrosion programme and experimental material samples evaluation. General view of the monitoring system is shown in Fig. 1.

scholarly journals USING AEROBIC SYNTROPHIC ASSOCIATIONS OF MICROORGANISMS FOR THE DECONTAMINATION OF LIQUID RADIOACTIVE WASTE

2018 ◽  
Vol 13 (6) ◽  
pp. 52-59
Author(s):  
N. V. Klochkova ◽  
A. V. Ananyev ◽  
N. Yu. Pozdnyakova ◽  
A. A. Savelyev
Keyword(s):  
Radioactive Waste ◽  
Time Dependence ◽  
New Technology ◽  
Liquid Radioactive Waste ◽  
Primary Objective ◽  
Biological Origin ◽  
Syntrophic Association ◽  
Cesium 137 ◽  
Ph Range ◽  
Barium Isotope

The primary objective of the study was to test the possibility of cesium-137 transmutation into a stable barium isotope in contact with an aerobic syntrophic association (SA - a conglomerate of several thousands of different species of bacteria, protozoa and fungi living in symbiosis with each other) together with a set of macro- and microelements. The study was performed sequentially on two different SA. In the course of the work, the transmutation of cesium-137 into stable barium with the use of SA was not experimentally revealed, but the phenomenon of cesium-137 biosorption by both SA was detected to different degrees. In the course of the experiment the possibility of cesium-137 sorption by SA from the solution in the pH range of 7.7 - 8.6 was shown. In the process of the work, the time dependence of cesium-137 distribution in the liquid phase and the phase of SA was determined. The time dependence of the sorption capacity of the syntrophic association was revealed. With further continuation of the study, it is possible to obtain a mixture of SA capable of selectively extracting and concentrating prescribed radionuclides from the liquid phase.The result of this work may be the development of a technology for processing and conditioning low-level liquid radioactive waste (RW) by transferring the bulk of radioisotopes in the phase of SA (the so-called "nanosorbent of biological origin"), with multiple volume reduction.The cost of such a technology compared to existing technologies using synthetic sorbents should be several times less due to the cheapness of the SA and the reagents required for it. Besides, the new technology is more environmentally friendly. The process of biotechnologyoxidation of sulfide ores and concentrates based on the activity of chemolitotrophic bacteria that translate insoluble metal sulfides into soluble metal sulfates can serve as analogue for hardware design of RW purification technology using nanosorbent of biological origin.

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).

Structural Characterization of Immobilized Waste Forms Containing Secondary Waste from the Liquid Radioactive Waste Treatment

2019 ◽  
Vol 1151 ◽  
pp. 35-40
Author(s):  
Laura Ionascu ◽  
Mihaela Nicu ◽  
Felicia Dragolici
Keyword(s):  
Radioactive Waste ◽  
Structural Investigation ◽  
Nuclear Reactor ◽  
Waste Treatment ◽  
Liquid Radioactive Waste ◽  
Cement Matrix ◽  
Complexing Agents ◽  
X Ray Diffraction ◽  
X Ray

Aqueous liquid radioactive waste is generated during nuclear reactor operations and during industrial and institutional application of radioisotopes. The immobilization of radioactive waste in Portland cement matrix is the most used method, applied in the world by the countries developing nuclear energy programs. The conditioning of the radioactive wastes by cementation process imposes the structural investigation by X-ray diffraction (XRD) of the samples prepared with cement and different ratio of concentrate. This paper gives useful information about the influence of complexing agents related to damages produced in concrete microstructures.

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