liquid radioactive waste
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2021 ◽  
Vol 13 (4) ◽  
pp. 501-508
Author(s):  
Alla A. Kornilova ◽  
◽  
Vladimir I. Vysotskii ◽  
Sergey N. Gaydamaka ◽  
Marina A. Gladchenko ◽  
...  

It was found during the research that in the experimental and control bioreactors, which at the beginning of the experiments contained only cesium and strontium, by the end of the experiments, yttrium and barium were found. These isotopes are formed as a result of low-energy nuclear reactions involving protons. In addition, in experimental bioreactors with an optimal composition, a two to threefold increase in the concentration of yttrium was recorded in comparison with the control non-optimal experiments. Accumulation of strontium and cesium in biomass was registered, which is explained by the process of biosorption. It is known that biosorption is the first step towards nuclear transformation (biotransmutation). At the same time, one of the main conditions for the nuclear transformation of biomass elements is its maximum efficient growth. An unexpected fact discovered during the experiment is that yttrium and barium were also found in the control bioreactor, where no biomass was added before the experiment, but only deionized water, glucose, and the initial stable cesium and strontium salts. It is important to note that these elements were not detected in the analysis of the initial salts, substrates, and deionized water. Most likely, the presence of yttrium and barium is due to inoculation of the control fluid of the bioreactor (where no biomass pellets were added) with microorganisms from the experimental bioreactors during their periodic opening for taking current pH samples and adding glucose. Also, the work recorded a decrease in the content of cesium and strontium in the liquid by 20% and 55%, respectively, which goes beyond the statistical error.


Nukleonika ◽  
2021 ◽  
Vol 66 (4) ◽  
pp. 153-158
Author(s):  
Leon Fuks ◽  
Agata Oszczak-Nowińska

Abstract The sorption of 241Am3+, 85Sr2+ and 137Cs+ by calcium, strontium and barium alginates has been studied under different operation conditions. The most prominent adsorption was found in the pH range of 5–6 for all systems, even if the observed dependence on the acidity of the solution was small. The most favourable time for the adsorption process was found to be about 2 h for calcium alginate and 4 h for the other two sorbents.


PLoS ONE ◽  
2021 ◽  
Vol 16 (10) ◽  
pp. e0257605
Author(s):  
Marina O. Degteva ◽  
Evgenia I. Tolstykh ◽  
Elena A. Shishkina ◽  
Pavel A. Sharagin ◽  
Vladimir I. Zalyapin ◽  
...  

The objective of this study is to develop a skeleton model for assessing active marrow dose from bone-seeking beta-emitting radionuclides. This article explains the modeling methodology which accounts for individual variability of the macro- and microstructure of bone tissue. Bone sites with active hematopoiesis are assessed by dividing them into small segments described by simple geometric shapes. Spongiosa, which fills the segments, is modeled as an isotropic three-dimensional grid (framework) of rod-like trabeculae that “run through” the bone marrow. Randomized multiple framework deformations are simulated by changing the positions of the grid nodes and the thickness of the rods. Model grid parameters are selected in accordance with the parameters of spongiosa microstructures taken from the published papers. Stochastic modeling of radiation transport in heterogeneous media simulating the distribution of bone tissue and marrow in each of the segments is performed by Monte Carlo methods. Model output for the human femur at different ages is provided as an example. The uncertainty of dosimetric characteristics associated with individual variability of bone structure was evaluated. An advantage of this methodology for the calculation of doses absorbed in the marrow from bone-seeking radionuclides is that it does not require additional studies of autopsy material. The biokinetic model results will be used in the future to calculate individual doses to members of a cohort exposed to 89,90Sr from liquid radioactive waste discharged to the Techa River by the Mayak Production Association in 1949–1956. Further study of these unique cohorts provides an opportunity to gain more in-depth knowledge about the effects of chronic radiation on the hematopoietic system. In addition, the proposed model can be used to assess the doses to active marrow under any other scenarios of 90Sr and 89Sr intake to humans.


Processes ◽  
2021 ◽  
Vol 9 (9) ◽  
pp. 1679
Author(s):  
Giorgi Nabakhtiani ◽  
Irma Giorgadze ◽  
Michael I. Ojovan

50 m3 of legacy liquid radioactive waste at the Saakadze site in Georgia was treated using a modular type facility with apparatuses encased in three metallic 200 L drums using as purification method the sorption/ion exchange technology. The main contaminant of water in the underground tank was the long-lived radionuclide 226Ra. The casing of processing equipment enabled an effective conditioning of all secondary waste at the end of treatment campaign which resulted in the fully purified water stored on site for further reuse or discharge, and three 200 L metallic drums with cemented radioactive waste which are currently safely stored.


Author(s):  
O. B. Korenkova ◽  
A. V. Radkevich ◽  
N. I. Voronik

The paper presents the results of 106Ru radionuclide behavior regularities study in aqueous solutions in a wide pH range by ultrafiltration, ion exchange and centrifugation methods. The regions of 106Ru various species existence in solution have been established: cationic 106Ru species at pH < 3.5; the transition region of non-ionic species formation in the range of pH 3.5–4.2 and the region of non-ionic species predominant formation at pH > 4.2. A characteristic feature of the studied solutions is the formation of non-ionic particles by microconcentrations of 106Ru via pseudocolloids at lower pH values as compared to ruthenium solutions with a concentration of 10-6–10-4 mol/dm3. The established regularities of the behavior of ruthenium radionuclides can be utilized to increase the efficiency of ion exchange and membrane separation methods at nuclear and radiation facilities for technological solutions and liquid radioactive waste treatment.


2021 ◽  
Vol 416 ◽  
pp. 125902
Author(s):  
Oleg A. Kononenko ◽  
Vitaly V. Milyutin ◽  
Vadim I. Makarenkov ◽  
Evgeny A. Kozlitin

Polymers ◽  
2021 ◽  
Vol 13 (15) ◽  
pp. 2520
Author(s):  
Arman B. Yeszhanov ◽  
Ilya V. Korolkov ◽  
Saule S. Dosmagambetova ◽  
Maxim V. Zdorovets ◽  
Olgun Güven

Membrane distillation (MD) is a rapidly developing field of research and finds applications in desalination of water, purification from nonvolatile substances, and concentration of various solutions. This review presents data from recent studies on the MD process, MD configuration, the type of membranes and membrane hydrophobization. Particular importance has been placed on the methods of hydrophobization and the use of track-etched membranes (TeMs) in the MD process. Hydrophobic TeMs based on poly(ethylene terephthalate) (PET), poly(vinylidene fluoride) (PVDF) and polycarbonate (PC) have been applied in the purification of water from salts and pesticides, as well as in the concentration of low-level liquid radioactive waste (LLLRW). Such membranes are characterized by a narrow pore size distribution, precise values of the number of pores per unit area and narrow thickness. These properties of membranes allow them to be used for more accurate water purification and as model membranes used to test theoretical models (for instance LEP prediction).


2021 ◽  
Author(s):  
Alexander V. Vodovatov

The development of radiation medicine in the Russian Federation has resulted in the improvement of the regulatory and methodological framework for radiation safety regulation. The main obstacle for the development of radionuclide therapy in the Russian Federation is the liquid radioactive waste management (mainly urine and faeces of patients) generated during radionuclide therapy on an ambulatory basis (day patient department). The paper presents a brief analysis of the current domestic and international regulatory liquid radionuclide waste management documents. It has been shown that there is no strategy for solving the problem of utilizing biological waste from patients during radionuclide therapy. Long-term task for ensuring the sanitary and epidemiological well-being of the population of the Russian Federation could be the solution for the problem.


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