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/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/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}
Pub Date : 2024-04-23DOI: 10.1134/s1066362224010028
K. V. Martynov, V. V. Kulemin, E. P. Krasavina, I. A. Rumer, Yu. M. Nevolin, S. A. Kulyukhin
Abstract
This work examines cast stone matrices (CSM) fabricated by comelting basalt and Sr, Ln (Ce, Nd, Gd) oxides. Matrices containing glass and clinopyroxene as the major phases were established to be resulted from the comelting of basalt with SrO. Strontium partially replaces calcium in clinopyroxene, but mostly enriches the melt in contact with crystallizing clinopyroxene. When this melt cools, glass is formed containing up to 31 wt % SrO. The doping of basalt with oxides of rare earth elements (REE) MxOy: CeO2, Nd2O3, Gd2O3 taken in a weight ratio of 4 : 1 and 2 : 1, results in the formation of CSM, the main permanent phases of which are glass and clinopyroxene. In addition, magnesioferrite can crystallize from a basaltic melt upon cooling, and phases of cerianite CeO2 or britholite Ca(Nd,Gd)4(SiO4)3O can crystallize depending on the basalt/MxOy weight ratio.
{"title":"Cast Stone Matrix Based on Comelts of Basalt and Metal Oxides: Part I. System Basalt–MxOy (M = Sr, Ln)","authors":"K. V. Martynov, V. V. Kulemin, E. P. Krasavina, I. A. Rumer, Yu. M. Nevolin, S. A. Kulyukhin","doi":"10.1134/s1066362224010028","DOIUrl":"https://doi.org/10.1134/s1066362224010028","url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>This work examines cast stone matrices (CSM) fabricated by comelting basalt and Sr, Ln (Ce, Nd, Gd) oxides. Matrices containing glass and clinopyroxene as the major phases were established to be resulted from the comelting of basalt with SrO. Strontium partially replaces calcium in clinopyroxene, but mostly enriches the melt in contact with crystallizing clinopyroxene. When this melt cools, glass is formed containing up to 31 wt % SrO. The doping of basalt with oxides of rare earth elements (REE) M<sub><i>x</i></sub>O<sub><i>y</i></sub>: CeO<sub>2</sub>, Nd<sub>2</sub>O<sub>3</sub>, Gd<sub>2</sub>O<sub>3</sub> taken in a weight ratio of 4 : 1 and 2 : 1, results in the formation of CSM, the main permanent phases of which are glass and clinopyroxene. In addition, magnesioferrite can crystallize from a basaltic melt upon cooling, and phases of cerianite CeO<sub>2</sub> or britholite Ca(Nd,Gd)<sub>4</sub>(SiO<sub>4</sub>)<sub>3</sub>O can crystallize depending on the basalt/M<sub><i>x</i></sub>O<sub><i>y</i></sub> weight ratio.</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":"140804153","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/s1066362224010065
M. V. Mamchich, A. A. Naumov, N. D. Goletskii, E. A. Puzikov, A. N. Viznyi>, A. V. Bizin, A. I. Medvedeva
Abstract
Centrifugal contactor rig trials of the partitioning flowsheet were carried out using simulated and real high level waste solutions obtained by reprocessing of WWER-100 spent nuclear fuel with burn-up of 47 MW day/t. 40% TBP in Isopar M was used as a solvent with magnesium nitrate as a salting-out agent. Complete removal of Cs, Sr, Zr, and Mo to raffinate was achieved. Rare earth elements, Am and Cm were totally concentrated in TPE and REE product. Comparison of the results of this work and previous trials with iron(III) nitrate as a salting-out agent [1] demonstrated that the use of magnesium nitrate instead of iron(III) nitrate resulted in higher decontamination factors of TPE and REE fraction from Cs (about 10 000) while in the case of iron(III) nitrate they are >7500.
摘要 利用对 WWER-100 型乏核燃料（烧失量为 47 兆瓦/天/吨）进行后处理所获得的模拟和实际高浓度废液，对分馏流程图进行了离心接触器钻机试验。使用 Isopar M 中的 40% TBP 作为溶剂，硝酸镁作为除盐剂。铯、锶、锆和钼被完全去除。稀土元素 Am 和 Cm 完全浓缩在 TPE 和 REE 产品中。将这项工作的结果与之前使用硝酸铁（III）作为除盐剂的试验结果[1]进行比较后发现，使用硝酸镁而不是硝酸铁（III）可提高 TPE 和稀土元素馏分的除铯系数（约 10 000），而使用硝酸铁（III）的除铯系数为 7500。
{"title":"Partitioning of the High Level Radioactive Waste from the Purex Process by 40% TBF in Isoparaffin Using Magnesium Nitrate as a Salting-out Agent","authors":"M. V. Mamchich, A. A. Naumov, N. D. Goletskii, E. A. Puzikov, A. N. Viznyi>, A. V. Bizin, A. I. Medvedeva","doi":"10.1134/s1066362224010065","DOIUrl":"https://doi.org/10.1134/s1066362224010065","url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>Centrifugal contactor rig trials of the partitioning flowsheet were carried out using simulated and real high level waste solutions obtained by reprocessing of WWER-100 spent nuclear fuel with burn-up of 47 MW day/t. 40% TBP in Isopar M was used as a solvent with magnesium nitrate as a salting-out agent. Complete removal of Cs, Sr, Zr, and Mo to raffinate was achieved. Rare earth elements, Am and Cm were totally concentrated in TPE and REE product. Comparison of the results of this work and previous trials with iron(III) nitrate as a salting-out agent [1] demonstrated that the use of magnesium nitrate instead of iron(III) nitrate resulted in higher decontamination factors of TPE and REE fraction from Cs (about 10 000) while in the case of iron(III) nitrate they are >7500.</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":"140804130","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/s1066362224010016
O. S. Dmitrieva, M. G. Dmitriev, A. Yu. Shadrin, D. A. Kapralov, A. S. Kornilov, A. A. Pylaeva, O. N. Nikitin
Abstract
The method of fabrication of solid solution powder of uranium/plutonium (38%) oxides from the pulp of ammonium uranyl-plutonyl carbonate process (AUPuC) by microwave radiation in reducing and atmospheric environments was proposed and tested at the laboratory level. For research the pulp was prepared, obtained by co-precipitation of uranium and plutonium from nitrate solution (simulator for stripping product). The process consists of three main stages: oxidation of Pu(IV) to Pu(VI), precipitation, and conversion in a laboratory microwave unit. According to data of the X-ray diffraction analysis the powders synthesized in a reducing atmosphere and an atmospheric environment are a solid cubic solution (UxPu1–x)O2 and (PuO2, U3O8) mixed oxide, respectively. Scanning electron microscopy and electron probe microanalysis of the powder obtained in an atmospheric environment showed a fairly uniform distribution of U, Pu, and O in the solid phase.
摘要 提出了在还原和大气环境中通过微波辐射从碳酸铀酰-钚铵工艺（AUPuC）浆料中制造铀/钚（38%）氧化物固溶体粉末的方法，并在实验室进行了测试。为进行研究，制备了铀和钚从硝酸盐溶液（剥离产品模拟器）中共沉淀得到的纸浆。该过程包括三个主要阶段：钚（IV）氧化成钚（VI）、沉淀和在实验室微波装置中进行转化。根据 X 射线衍射分析数据，在还原气氛和大气环境中合成的粉末分别是固体立方溶液 (UxPu1-x)O2 和 (PuO2, U3O8) 混合氧化物。在大气环境中获得的粉末的扫描电子显微镜和电子探针显微分析表明，U、Pu 和 O 在固相中的分布相当均匀。
{"title":"Preparation of Uranium/Plutonium Oxide Solid Solution Powder from Ammonium Uranyl–Plutonyl Carbonate in a Laboratory Microwave Unit","authors":"O. S. Dmitrieva, M. G. Dmitriev, A. Yu. Shadrin, D. A. Kapralov, A. S. Kornilov, A. A. Pylaeva, O. N. Nikitin","doi":"10.1134/s1066362224010016","DOIUrl":"https://doi.org/10.1134/s1066362224010016","url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>The method of fabrication of solid solution powder of uranium/plutonium (38%) oxides from the pulp of ammonium uranyl-plutonyl carbonate process (AUPuC) by microwave radiation in reducing and atmospheric environments was proposed and tested at the laboratory level. For research the pulp was prepared, obtained by co-precipitation of uranium and plutonium from nitrate solution (simulator for stripping product). The process consists of three main stages: oxidation of Pu(IV) to Pu(VI), precipitation, and conversion in a laboratory microwave unit. According to data of the X-ray diffraction analysis the powders synthesized in a reducing atmosphere and an atmospheric environment are a solid cubic solution (U<sub><i>x</i></sub>Pu<sub>1–<i>x</i></sub>)O<sub>2</sub> and (PuO<sub>2</sub>, U<sub>3</sub>O<sub>8</sub>) mixed oxide, respectively. Scanning electron microscopy and electron probe microanalysis of the powder obtained in an atmospheric environment showed a fairly uniform distribution of U, Pu, and O in the solid phase.</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":"140804196","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}
扫码关注我们
求助内容：
应助结果提醒方式：
京公网安备 11010802042870号