scholarly journals ASSESSMENT OF RADIATION AND TEMPERATURE LOADS ON CEMENT COMPOUND CONTAINING SIMULATED RADIOACTIVE WASTE

2020 ◽  
Vol 10 (1) ◽  
pp. 66-72
Author(s):  
A. P. Varlakov ◽  
◽  
A. A. Zherebtsov ◽  
V. G. Petrov ◽  
V. V. Kapustin ◽  
...  
Author(s):  
Andrey P. Varlakov ◽  
Konstantin M. Efimov ◽  
Valeri N. Tchernonojkine ◽  
Aleksandr S. Barinov ◽  
Olga A. Gorbunova

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.


Author(s):  
S. A. Dmitriev ◽  
A. P. Varlakov ◽  
A. V. Germanov ◽  
O. A. Gorbunova ◽  
A. S. Barinov ◽  
...  

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.


Author(s):  
Tatiana Kulagina ◽  
Vladimir Kulagin ◽  
Eleonora Nikiforova ◽  
Dmitriy Prikhodov ◽  
Alexander Shimanskiy ◽  
...  

Author(s):  
Andrey P. Varlakov ◽  
Olga A. Gorbunova ◽  
Aleksandr S. Barinov ◽  
Vadim A. Iljin ◽  
Konstantin M. Efimov ◽  
...  

Abstract In order to prevent biological corrosion of cement compound containing radioactive waste, it is proposed to use biocidal additives of polyhexamethyleneguanidines (PHMG), which have a wide range of biocidal activity. It has been shown that inclusion of biocidal additives of polyhexamethyleneguanidines in quantities 0,25–2% wt. into the grout used for the solidification of radioactive waste (RW) or for recovering the integrity of old RW repositories provides the necessary bacteriostatic and biocidal protection of cement compound and improves all the regulated properties — compression strength, Cs-137 leaching rate, frost-resistance, radiation resistance and long term water resistance.


MRS Advances ◽  
2020 ◽  
Vol 5 (3-4) ◽  
pp. 121-129
Author(s):  
Vladimir A. Kashcheev ◽  
Nikolay D. Musatov ◽  
Michael I. Ojovan

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).


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