Pub Date : 2024-04-23DOI: 10.1134/s1066362224010090
V. V. Kulemin, I. A. Rumer, Yu. M. Nevolin, E. P. Krasavina, S. A. Kulyukhin
Abstract
The release of 137Cs into an Ar flow during the reaction of 137CsI and 137CsOH–137Cs2CO3 with molten lead at a temperature of ~852 K was studied. It was determined that during the heating of Pb0 with 137CsI, 137CsOH–137Cs2CO3, and 137CsI–137CsOH–137Cs2CO3 from 2 to 8% of 137Cs can pass into the gas flow. Based on the distribution of 137Cs among the elements of the gas purification system, it was concluded that the chemical and disperse composition of the compounds containing 137Cs in the gas phase is fairly heterogeneous. Volatile 137Cs compounds formed on heating 137CsI, 137CsOH–137Cs2CO3, and 137CsI–137CsOH–137Cs2CO3 with Pb0 in a gas flow at ~852 K can contain both charged aerosols and aerosols without an electric charge.
{"title":"Release of 137Cs into the Gas Phase during the Interaction of 137Cs Compounds with Molten Lead","authors":"V. V. Kulemin, I. A. Rumer, Yu. M. Nevolin, E. P. Krasavina, S. A. Kulyukhin","doi":"10.1134/s1066362224010090","DOIUrl":"https://doi.org/10.1134/s1066362224010090","url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>The release of <sup>137</sup>Cs into an Ar flow during the reaction of <sup>137</sup>CsI and <sup>137</sup>CsOH–<sup>137</sup>Cs<sub>2</sub>CO<sub>3</sub> with molten lead at a temperature of ~852 K was studied. It was determined that during the heating of Pb<sup>0</sup> with <sup>137</sup>CsI, <sup>137</sup>CsOH–<sup>137</sup>Cs<sub>2</sub>CO<sub>3</sub>, and <sup>137</sup>CsI–<sup>137</sup>CsOH–<sup>137</sup>Cs<sub>2</sub>CO<sub>3</sub> from 2 to 8% of <sup>137</sup>Cs can pass into the gas flow. Based on the distribution of <sup>137</sup>Cs among the elements of the gas purification system, it was concluded that the chemical and disperse composition of the compounds containing <sup>137</sup>Cs in the gas phase is fairly heterogeneous. Volatile <sup>137</sup>Cs compounds formed on heating <sup>137</sup>CsI, <sup>137</sup>CsOH–<sup>137</sup>Cs<sub>2</sub>CO<sub>3</sub>, and <sup>137</sup>CsI–<sup>137</sup>CsOH–<sup>137</sup>Cs<sub>2</sub>CO<sub>3</sub> with Pb<sup>0</sup> in a gas flow at ~852 K can contain both charged aerosols and aerosols without an electric charge.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":null,"pages":null},"PeriodicalIF":0.9,"publicationDate":"2024-04-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140804193","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-04-23DOI: 10.1134/s1066362224010120
N. G. Guliyeva, L. Yu. Jabbarova, I. I. Mustafayev, S. F. Aliyeva-Chichek
Abstract
The effect of gamma radiation on olefins was studied under static conditions at an absorbed dose of 65 kGy and at a dose rate of P = 0.076 Gy/s. The effect of radiation on the physicochemical characteristics and structural and group composition of the resulting olefins has been established. Post-radiation effects were studied immediately after irradiation and during 1, 2, 4, and 7 months later. When fuels are irradiated, polymerization of unsaturated hydrocarbons occurs. After the irradiation cessation, there occurs postpolymerization process. The chemical instability of olefins in fuels leads to the formation of carbon deposits in the engine system, tanks, and valves. IR spectra, iodine values, density, and kinematic viscosity of irradiated samples were measured.
{"title":"Influence of Gamma Radiation on the Composition and Physicochemical Characteristics of Olefins: Post-Radiation Effects","authors":"N. G. Guliyeva, L. Yu. Jabbarova, I. I. Mustafayev, S. F. Aliyeva-Chichek","doi":"10.1134/s1066362224010120","DOIUrl":"https://doi.org/10.1134/s1066362224010120","url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>The effect of gamma radiation on olefins was studied under static conditions at an absorbed dose of 65 kGy and at a dose rate of <i>P</i> = 0.076 Gy/s. The effect of radiation on the physicochemical characteristics and structural and group composition of the resulting olefins has been established. Post-radiation effects were studied immediately after irradiation and during 1, 2, 4, and 7 months later. When fuels are irradiated, polymerization of unsaturated hydrocarbons occurs. After the irradiation cessation, there occurs postpolymerization process. The chemical instability of olefins in fuels leads to the formation of carbon deposits in the engine system, tanks, and valves. IR spectra, iodine values, density, and kinematic viscosity of irradiated samples were measured.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":null,"pages":null},"PeriodicalIF":0.9,"publicationDate":"2024-04-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140804187","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-04-23DOI: 10.1134/s1066362224010119
N. G. Guliyeva, I. I. Mustafayev, S. F. Aliyeva-Chichek, F. A. Chichek
Abstract
Protecting soil from pollution by oil and petroleum products is an important environmental task. Sources of oil contamination of soil are not only oil fields, but also industrial facilities that directly or indirectly use petroleum products. Of interest are studies aimed at studying the processes of changes in oil during its degradation in the soil. When oil degrades, polycondensation processes occur on the soil surface, which leads to structural changes in the oil. We compared the composition and properties of oil after production and long-term presence on the soil surface. An analysis of oil-contaminated soils was carried out at a distance of 0–5 and 0–10 m from the source of pollution and from a depth of 0–15 cm. Oils degraded in the soil are also susceptible to the effects of natural radionuclide background. In this regard, the work investigated the impact of gamma radiation on oil degraded in the soil of the Surakhani oil field of Azerbaijan. Oil samples were taken from a well and from oil-contaminated soil and separated into three components: oils, resins, and asphaltenes. The results of mass spectrometric and IR spectrometric studies of the indicated fractions of crude and degraded oil samples are presented, and the patterns of formation of gaseous products during their radiolysis are established.
{"title":"Influence of Soil Degradation on Radiation-Chemical Transformations of Oil","authors":"N. G. Guliyeva, I. I. Mustafayev, S. F. Aliyeva-Chichek, F. A. Chichek","doi":"10.1134/s1066362224010119","DOIUrl":"https://doi.org/10.1134/s1066362224010119","url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>Protecting soil from pollution by oil and petroleum products is an important environmental task. Sources of oil contamination of soil are not only oil fields, but also industrial facilities that directly or indirectly use petroleum products. Of interest are studies aimed at studying the processes of changes in oil during its degradation in the soil. When oil degrades, polycondensation processes occur on the soil surface, which leads to structural changes in the oil. We compared the composition and properties of oil after production and long-term presence on the soil surface. An analysis of oil-contaminated soils was carried out at a distance of 0–5 and 0–10 m from the source of pollution and from a depth of 0–15 cm. Oils degraded in the soil are also susceptible to the effects of natural radionuclide background. In this regard, the work investigated the impact of gamma radiation on oil degraded in the soil of the Surakhani oil field of Azerbaijan. Oil samples were taken from a well and from oil-contaminated soil and separated into three components: oils, resins, and asphaltenes. The results of mass spectrometric and IR spectrometric studies of the indicated fractions of crude and degraded oil samples are presented, and the patterns of formation of gaseous products during their radiolysis are established.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":null,"pages":null},"PeriodicalIF":0.9,"publicationDate":"2024-04-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140804189","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-04-23DOI: 10.1134/s1066362224010144
M. M. Domanov
Abstract
The features of the concentration distribution of 238U, 232Th, and 226Ra in the surface layer in the bottom sediments of the shelf and continental slope of Svalbard are considered. The content of 226Ra, 232Th, and 238U varied in the range 22–134.3, 22.4–50.9, and 10.9–37.7 Bq/kg, respectively. The amount of 226Ra nonequilibrium with 238U (226Raex) ranged from 23 to 73% of the total 226Ra content in sediments. The maximum concentrations of 226Ra, 238U, 232Th, and 226Raex (134.3, 37.7, 50.9, and 98.2 Bq/kg, respectively) were obtained in the area of increased bioproductivity (Eagle Trough). In this zone, the relationship between the concentrations of 226Ra and 226Raex with the content of organic matter in sediment is well expressed, the correlation coefficients are R = 0.94 and 0.92, respectively, which indicates a significant contribution of the biological community to the accumulation of 226Ra in bottom sediments. The 226Ra concentration and the 226Ra excess value are negatively related to the redox potential of the sediment (R = –0.88). This pattern is also true in other areas of the Svalbard waters. In general, for the entire array of observations, the concentrations of 238U and 232Th increase with increasing content of organic carbon in the sediment (R = 0.72 and 0.7, respectively). The concentrations of 238U and 232Th decrease with increasing Ccarb content in the sediment (R = –0.79 and –0.81, respectively). The data obtained indicate the need to take into account the 226Ra excess when assessing the total natural radioactivity of marine sediments, the value of which may exceed the radioactivity of 238U and 232Th.
{"title":"Distribution Features of 238U, 232Th, and 226Ra in Bottom Sediments of the Shelf and Continental Slope of Svalbard","authors":"M. M. Domanov","doi":"10.1134/s1066362224010144","DOIUrl":"https://doi.org/10.1134/s1066362224010144","url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>The features of the concentration distribution of <sup>238</sup>U, <sup>232</sup>Th, and <sup>226</sup>Ra in the surface layer in the bottom sediments of the shelf and continental slope of Svalbard are considered. The content of <sup>226</sup>Ra, <sup>232</sup>Th, and <sup>238</sup>U varied in the range 22–134.3, 22.4–50.9, and 10.9–37.7 Bq/kg, respectively. The amount of <sup>226</sup>Ra nonequilibrium with <sup>238</sup>U (<sup>226</sup>Ra<sub>ex</sub>) ranged from 23 to 73% of the total <sup>226</sup>Ra content in sediments. The maximum concentrations of <sup>226</sup>Ra, <sup>238</sup>U, <sup>232</sup>Th, and <sup>226</sup>Ra<sub>ex</sub> (134.3, 37.7, 50.9, and 98.2 Bq/kg, respectively) were obtained in the area of increased bioproductivity (Eagle Trough). In this zone, the relationship between the concentrations of <sup>226</sup>Ra and <sup>226</sup>Ra<sub>ex</sub> with the content of organic matter in sediment is well expressed, the correlation coefficients are <i>R</i> = 0.94 and 0.92, respectively, which indicates a significant contribution of the biological community to the accumulation of <sup>226</sup>Ra in bottom sediments. The <sup>226</sup>Ra concentration and the <sup>226</sup>Ra excess value are negatively related to the redox potential of the sediment (<i>R</i> = –0.88). This pattern is also true in other areas of the Svalbard waters. In general, for the entire array of observations, the concentrations of <sup>238</sup>U and <sup>232</sup>Th increase with increasing content of organic carbon in the sediment (<i>R</i> = 0.72 and 0.7, respectively). The concentrations of <sup>238</sup>U and <sup>232</sup>Th decrease with increasing <i>C</i><sub>carb</sub> content in the sediment (<i>R</i> = –0.79 and –0.81, respectively). The data obtained indicate the need to take into account the <sup>226</sup>Ra excess when assessing the total natural radioactivity of marine sediments, the value of which may exceed the radioactivity of <sup>238</sup>U and <sup>232</sup>Th.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":null,"pages":null},"PeriodicalIF":0.9,"publicationDate":"2024-04-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140804195","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-04-23DOI: 10.1134/s1066362224010089
V. V. Kulemin, S. A. Kulyukhin
Abstract
The possibility of using the polymer sorbent Polysorb-1 for the treatment of nitric acid solutions to remove organophosphorus compounds, including tributyl phosphate (TBP) and hexachlorobutadiene (HCBD), is studied. It is shown that decontamination of nitric acid solutions containing organophosphorus compounds, HCBD, U(VI), and Pu(IV) with Polysorb-1 sorbent under dynamic conditions allows reducing the phosphorus and HCBD content to ~2 mg/dm3 or less and to 0.05 mg/dm3 or less, respectively. In this case, sorption of U(VI) and Pu(IV) does not occur. The procedures of vacuum distillation and overheated steam stripping are described for regeneration of Polysorb-1 sorbent containing TBP and HCBD. The optimal process temperature was chosen to be 170°C.
{"title":"Sorption Treatment of Nitric Acid Solutions to Remove Tributyl Phosphate and Hexachlorobutadiene","authors":"V. V. Kulemin, S. A. Kulyukhin","doi":"10.1134/s1066362224010089","DOIUrl":"https://doi.org/10.1134/s1066362224010089","url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>The possibility of using the polymer sorbent Polysorb-1 for the treatment of nitric acid solutions to remove organophosphorus compounds, including tributyl phosphate (TBP) and hexachlorobutadiene (HCBD), is studied. It is shown that decontamination of nitric acid solutions containing organophosphorus compounds, HCBD, U(VI), and Pu(IV) with Polysorb-1 sorbent under dynamic conditions allows reducing the phosphorus and HCBD content to ~2 mg/dm<sup>3</sup> or less and to 0.05 mg/dm<sup>3</sup> or less, respectively. In this case, sorption of U(VI) and Pu(IV) does not occur. The procedures of vacuum distillation and overheated steam stripping are described for regeneration of Polysorb-1 sorbent containing TBP and HCBD. The optimal process temperature was chosen to be 170°C.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":null,"pages":null},"PeriodicalIF":0.9,"publicationDate":"2024-04-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140804329","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-04-23DOI: 10.1134/s1066362224010053
A. A. Naumov, N. D. Goletskii, E. A. Puzikov, M. V. Mamchich, A. S. Kudinov
Abstract
Results of centrifugal contactor rig trials of the flowsheet of the first solvent extraction cycle in protective glove boxes using simulated solutions of spent nuclear fuel and 30 and 45% TBP in isoparaffin as a solvent are compared. It was shown that an increase in the TBP concentration to 45% resulted in deterioration of the quality of the products obtained by the same flowsheets with 30% TBP in Isopar L as a solvent. Comparison of experimental and computer simulated profiles of component distribution across the stages of extraction units demonstrated satisfactory agreement in nitric acid and uranium concentrations. At the same time, it was found that simulation model of zirconium, technetium, and neptunium extraction requires improvement considering interaction of these elements with complexing agents.
{"title":"Comparison of Dynamic Tests of the Modified Purex Process Flowsheet Using 30 and 45% TBF in Isoparaffin","authors":"A. A. Naumov, N. D. Goletskii, E. A. Puzikov, M. V. Mamchich, A. S. Kudinov","doi":"10.1134/s1066362224010053","DOIUrl":"https://doi.org/10.1134/s1066362224010053","url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>Results of centrifugal contactor rig trials of the flowsheet of the first solvent extraction cycle in protective glove boxes using simulated solutions of spent nuclear fuel and 30 and 45% TBP in isoparaffin as a solvent are compared. It was shown that an increase in the TBP concentration to 45% resulted in deterioration of the quality of the products obtained by the same flowsheets with 30% TBP in Isopar L as a solvent. Comparison of experimental and computer simulated profiles of component distribution across the stages of extraction units demonstrated satisfactory agreement in nitric acid and uranium concentrations. At the same time, it was found that simulation model of zirconium, technetium, and neptunium extraction requires improvement considering interaction of these elements with complexing agents.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":null,"pages":null},"PeriodicalIF":0.9,"publicationDate":"2024-04-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140804197","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-04-23DOI: 10.1134/s1066362224010132
V. P. Shevchenko, K. V. Shevchenko, L. A. Andreeva, I. Yu. Nagaev, N. F. Myasoedov
Abstract
The efficiency of incorporating deuterium into 4-aminobutanoic acid (GABA) has been studied. The use of D2O at 200°C makes it possible to introduce into GABA an average of about 0.5 deuterium atoms, D2O with trifluoroacetic acid (1 : 1) at 250°C, an average 1.49 deuterium atoms with a yield of 15%. The solid-phase method permits introducing about 3 deuterium atoms per GABA molecule. During isotopic exchange with D2O, the use of a palladium–rhodium mixture pretreated with deuterium gas made it possible to produce [D]GABA with the deuterium content of 4.5–4.6 atoms. But in both cases, the yields of [D]GABA were low. Preparative amounts of [D]GABA were produced engaging additional supports. The best result was obtained when applying GABA to zeolite. Using D2O with 5% Pd/BaSO4–GABA–zeolite pretreated with deuterium gas, allows producing [D]GABA with an average content of 1.5–2.0 deuterium atoms and a yield of about 30%.
{"title":"The Use of D2 and Deuterated Water for the Introduction of a Label into 4-Aminobutanoic Acid","authors":"V. P. Shevchenko, K. V. Shevchenko, L. A. Andreeva, I. Yu. Nagaev, N. F. Myasoedov","doi":"10.1134/s1066362224010132","DOIUrl":"https://doi.org/10.1134/s1066362224010132","url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>The efficiency of incorporating deuterium into 4-aminobutanoic acid (GABA) has been studied. The use of D<sub>2</sub>O at 200°C makes it possible to introduce into GABA an average of about 0.5 deuterium atoms, D<sub>2</sub>O with trifluoroacetic acid (1 : 1) at 250°C, an average 1.49 deuterium atoms with a yield of 15%. The solid-phase method permits introducing about 3 deuterium atoms per GABA molecule. During isotopic exchange with D<sub>2</sub>O, the use of a palladium–rhodium mixture pretreated with deuterium gas made it possible to produce [D]GABA with the deuterium content of 4.5–4.6 atoms. But in both cases, the yields of [D]GABA were low. Preparative amounts of [D]GABA were produced engaging additional supports. The best result was obtained when applying GABA to zeolite. Using D<sub>2</sub>O with 5% Pd/BaSO<sub>4</sub>–GABA–zeolite pretreated with deuterium gas, allows producing [D]GABA with an average content of 1.5–2.0 deuterium atoms and a yield of about 30%.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":null,"pages":null},"PeriodicalIF":0.9,"publicationDate":"2024-04-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140804053","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-04-23DOI: 10.1134/s1066362224010041
K. V. Martynov, V. V. Kulemin, E. P. Krasavina, I. A. Rumer, G. V. Kostikova, S. A. Kulyukhin
Abstract
Phase formation in cast stone matrices (CSMs) fabricated through the interaction of comelted basalt with ZrO2 at 1623 K for 5 h on air was studied. Basalt melted under the above conditions contains two spinels (relict and newly formed), clinopyroxene of the composition Mg0.66Ca0.60Fe0.26Ti0.05Al0.66Si1.80O6, and glass as the major phases. When basalt is comelted with ZrO2, taken in a weight ratio of 1 : 1, CSMs containing zircon (ZrSiO4), glass, and baddeleyite (ZrO2) as the major phases are formed. Zirconium is concentrated mainly in two phases, zircon and baddeleyite. The rate of Zr leaching from the synthesized CSMs into H2O after 28 days is ~1.0 × 10–9 g/(cm2 day).
{"title":"Cast Stone Matrix Based on Comelts of Basalt and Metal Oxides. Part II. Basalt–ZrO2 System","authors":"K. V. Martynov, V. V. Kulemin, E. P. Krasavina, I. A. Rumer, G. V. Kostikova, S. A. Kulyukhin","doi":"10.1134/s1066362224010041","DOIUrl":"https://doi.org/10.1134/s1066362224010041","url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>Phase formation in cast stone matrices (CSMs) fabricated through the interaction of comelted basalt with ZrO<sub>2</sub> at 1623 K for 5 h on air was studied. Basalt melted under the above conditions contains two spinels (relict and newly formed), clinopyroxene of the composition Mg<sub>0.66</sub>Ca<sub>0.60</sub>Fe<sub>0</sub>.<sub>26</sub>Ti<sub>0.05</sub>Al<sub>0.66</sub>Si<sub>1.80</sub>O<sub>6</sub>, and glass as the major phases. When basalt is comelted with ZrO<sub>2</sub>, taken in a weight ratio of 1 : 1, CSMs containing zircon (ZrSiO<sub>4</sub>), glass, and baddeleyite (ZrO<sub>2</sub>) as the major phases are formed. Zirconium is concentrated mainly in two phases, zircon and baddeleyite. The rate of Zr leaching from the synthesized CSMs into H<sub>2</sub>O after 28 days is ~1.0 × 10<sup>–9</sup> g/(cm<sup>2</sup> day).</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":null,"pages":null},"PeriodicalIF":0.9,"publicationDate":"2024-04-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140804198","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-04-23DOI: 10.1134/s106636222401003x
K. V. Martynov, V. V. Kulemin, E. P. Krasavina, I. A. Rumer, G. V. Kostikova, Yu. M. Nevolin, S. A. Kulyukhin
Abstract
This work examines cast stone matrices (CSM) fabricated by comelting of basalt with both uranium-bearing perlite (M150 grade) and U3O8 at a temperature of 1623 K in air for 5 h. As a result of comelting of basalt with uranium-free M150 grade perlite, matrices are obtained containing glass and spinel as the major phases. When basalt is comelted with uranium-bearing perlite (M150 grade) CSMs are formed, the major phases of which are two Cr-spinels of different compositions, uranium-bearing glass, and dendritic aluminosilicate crystals. In the case of fusion of basalt and U3O8 taken in the initial weight ratio of 1 : 1, CSM is generated as the major phases containing UO3, CaU3O10, (Al,Cr,Fe)2U2O9, plagioclase, and uranium-bearing glass. The leaching rate of uranium from a basalt melt with uranium-bearing perlite (M150 grade, ~7.2 wt % U) and that of CSM made by comelting of basalt with U3O8, (~42.5 wt % U) after 28 days contact with water at 298 K was investigated.
本文研究了玄武岩与含铀珍珠岩（M150 级）和八氧化三铀在 1623 K 的温度下于空气中熔融 5 h 而形成的铸石基体（CSM）。玄武岩与含铀珍珠岩（M150 级）重熔后形成 CSM，其主要相为两种不同成分的铬尖晶石、含铀玻璃和树枝状铝硅酸盐晶体。如果玄武岩和八氧化三铀的初始重量比为 1:1，则生成的 CSM 的主要相为三氧化三铀、CaU3O10、（Al,Cr,Fe）2U2O9、斜长石和含铀玻璃。研究了含铀珍珠岩（M150 级，约 7.2 wt % U）的玄武岩熔体中铀的沥滤率，以及玄武岩与 U3O8（约 42.5 wt % U）在 298 K 温度下与水接触 28 天后熔融而成的 CSM 中铀的沥滤率。
{"title":"Uranium-Bearing Cast Stone Matrices","authors":"K. V. Martynov, V. V. Kulemin, E. P. Krasavina, I. A. Rumer, G. V. Kostikova, Yu. M. Nevolin, S. A. Kulyukhin","doi":"10.1134/s106636222401003x","DOIUrl":"https://doi.org/10.1134/s106636222401003x","url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>This work examines cast stone matrices (CSM) fabricated by comelting of basalt with both uranium-bearing perlite (M150 grade) and U<sub>3</sub>O<sub>8</sub> at a temperature of 1623 K in air for 5 h. As a result of comelting of basalt with uranium-free M150 grade perlite, matrices are obtained containing glass and spinel as the major phases. When basalt is comelted with uranium-bearing perlite (M150 grade) CSMs are formed, the major phases of which are two Cr-spinels of different compositions, uranium-bearing glass, and dendritic aluminosilicate crystals. In the case of fusion of basalt and U<sub>3</sub>O<sub>8</sub> taken in the initial weight ratio of 1 : 1, CSM is generated as the major phases containing UO<sub>3</sub>, CaU<sub>3</sub>O<sub>10</sub>, (Al,Cr,Fe)<sub>2</sub>U<sub>2</sub>O<sub>9</sub>, plagioclase, and uranium-bearing glass. The leaching rate of uranium from a basalt melt with uranium-bearing perlite (M150 grade, ~7.2 wt % U) and that of CSM made by comelting of basalt with U<sub>3</sub>O<sub>8</sub>, (~42.5 wt % U) after 28 days contact with water at 298 K was investigated.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":null,"pages":null},"PeriodicalIF":0.9,"publicationDate":"2024-04-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140804054","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-04-23DOI: 10.1134/s1066362224010077
V. V. Kulemin, G. V. Kostikova, S. A. Kulyukhin
Abstract
Sorption of tributyl phosphate (TBP) on a polymer sorbent Polysorb-1 in aqueous solutions and sorption of butylphosphoric acids onto layered Mg-Al double oxides and hydroxides in a 70% solution of TBP in dodecane was studied. It was found that the Polysorb-1 is suitable polymer sorbent to remove TBP in aqueous solutions in the static and dynamic modes, and LDH-Mg-Al-CD-OH is suitable sorbent to remove acidic products of the decomposition and hydrolysis of TBP in TBP solutions in dodecane.
{"title":"Sorption Treatment of Aqueous and Organic Media to Remove Tributyl Phosphate and Acidic Products of Its Decomposition","authors":"V. V. Kulemin, G. V. Kostikova, S. A. Kulyukhin","doi":"10.1134/s1066362224010077","DOIUrl":"https://doi.org/10.1134/s1066362224010077","url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>Sorption of tributyl phosphate (TBP) on a polymer sorbent Polysorb-1 in aqueous solutions and sorption of butylphosphoric acids onto layered Mg-Al double oxides and hydroxides in a 70% solution of TBP in dodecane was studied. It was found that the Polysorb-1 is suitable polymer sorbent to remove TBP in aqueous solutions in the static and dynamic modes, and LDH-Mg-Al-CD-OH is suitable sorbent to remove acidic products of the decomposition and hydrolysis of TBP in TBP solutions in dodecane.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":null,"pages":null},"PeriodicalIF":0.9,"publicationDate":"2024-04-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140806530","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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