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Joint Solubility of Uranyl(VI) and Plutonyl(VI) Nitrates in Nitric Acid Solutions
IF 0.9
Radiochemistry Pub Date : 2025-04-05 DOI: 10.1134/S1066362225010047
E. D. Filimonova, V. I. Volk
{"title":"Joint Solubility of Uranyl(VI) and Plutonyl(VI) Nitrates in Nitric Acid Solutions","authors":"E. D. Filimonova,&nbsp;V. I. Volk","doi":"10.1134/S1066362225010047","DOIUrl":"10.1134/S1066362225010047","url":null,"abstract":"<p>The solubility of plutonyl(VI) and uranyl(VI) nitrates in nitric acid solutions taken in the ratios Pu/(Pu + U) = 0.3 ± 0.015 (main data), Pu/(Pu + U) = 0.25 ± 0.025, and Pu/(Pu + U) = 0.5 ± 0.025 (single compositions) at +25, +15, and +5°C (±3) was determined by the method of isohydric crystallization. The calculated solubility isotherms of plutonyl(VI) and uranyl(VI) nitrates are presented in a wide range of nitric acid concentrations.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"67 1","pages":"25 - 30"},"PeriodicalIF":0.9,"publicationDate":"2025-04-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143784237","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}
引用次数: 0
Effect of Salting-Out Agents on the Extraction of Europium and Americium from Nitric Acid Solutions with 40% Tributyl Phosphate in a Hydrocarbon Diluent 脱盐剂对在碳氢化合物稀释液中用 40% 磷酸三丁酯从硝酸溶液中萃取铕和镅的影响
IF 0.9
Radiochemistry Pub Date : 2025-04-05 DOI: 10.1134/S1066362225010084
E. A. Puzikov, A. A. Naumov, P. I. Soroka, M. V. Mamchich, N. D. Goletskii, M. M. Metalidi, A. S. Kudinov
{"title":"Effect of Salting-Out Agents on the Extraction of Europium and Americium from Nitric Acid Solutions with 40% Tributyl Phosphate in a Hydrocarbon Diluent","authors":"E. A. Puzikov,&nbsp;A. A. Naumov,&nbsp;P. I. Soroka,&nbsp;M. V. Mamchich,&nbsp;N. D. Goletskii,&nbsp;M. M. Metalidi,&nbsp;A. S. Kudinov","doi":"10.1134/S1066362225010084","DOIUrl":"10.1134/S1066362225010084","url":null,"abstract":"<p>Experimental data on the extraction of nitric acid, europium, and americium with 40% TBP in C13 in the presence of salting-out agents such as sodium, magnesium, iron, and aluminum nitrates were obtained. The nitric acid and nitrate ion concentrations ensuring efficient recovery of transplutonium and rare earth elements were chosen. Based on the data obtained, the existing program for mathematical modeling (Statics, Dynamics program complexes) was adjusted. To check the adequacy of program operation, computations were made for the experimentally tested flowsheet of the high-level raffinate partitioning using the extraction system based on TBP in paraffin in the presence of a salting-out agent. Comparison of the calculation results with the results of cell-by-cell analysis of samples from the first block shows that the deviations are within the measurement uncertainty of the analytical equipment. The possibility of predicting the operation of the extraction cascade at varied parameters (phase flow rates, number of steps, salting-out agent concentration) was demonstrated.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"67 1","pages":"57 - 64"},"PeriodicalIF":0.9,"publicationDate":"2025-04-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143784078","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}
引用次数: 0
Sorption Treatment of Aqueous Solutions with Stirosorb Sorbent to Remove TBP 使用 Stirosorb 吸附剂对水溶液进行吸附处理以去除 TBP
IF 0.9
Radiochemistry Pub Date : 2025-04-05 DOI: 10.1134/S1066362225010096
V. V. Kulemin, S. A. Kulyukhin
{"title":"Sorption Treatment of Aqueous Solutions with Stirosorb Sorbent to Remove TBP","authors":"V. V. Kulemin,&nbsp;S. A. Kulyukhin","doi":"10.1134/S1066362225010096","DOIUrl":"10.1134/S1066362225010096","url":null,"abstract":"<p>The sorption treatment of aqueous solutions to remove TBP on the Stirosorb polymer sorbent in the batch and dynamic modes was studied. Stirosorb polymer sorbent allows removal of TBP from aqueous media at a solution temperature not exceeding 70°C to the residual organic matter content of no more than 10–11 mg/dm<sup>3</sup> at a load of ~0.9 g TBP/g sorbent. A solution containing U(VI) and Pu(IV) is decontaminated from phosphorus-containing compounds on Stirosorb sorbent without solution depletion of U(VI) and Pu(IV).</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"67 1","pages":"65 - 71"},"PeriodicalIF":0.9,"publicationDate":"2025-04-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143784079","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}
引用次数: 0
Deuterium Labeling of Dopaquine
IF 0.9
Radiochemistry Pub Date : 2025-02-17 DOI: 10.1134/S1066362224060122
V. P. Shevchenko, I. Yu. Nagaev, K. V. Shevchenko, N. F. Myasoedov
{"title":"Deuterium Labeling of Dopaquine","authors":"V. P. Shevchenko,&nbsp;I. Yu. Nagaev,&nbsp;K. V. Shevchenko,&nbsp;N. F. Myasoedov","doi":"10.1134/S1066362224060122","DOIUrl":"10.1134/S1066362224060122","url":null,"abstract":"<p>The possibility of introducing deuterium into dopaquine, a compound consisting of quinone and dopamine fragments, was examined. The isotope exchange can be carried out with deuterated water in the presence of trifluoroacetic acid (TFA) and HCl. The best results were obtained with TFA at 80°С. To activate isotope exchange, catalysts based on iridium or palladium (5% Pd/Al<sub>2</sub>O<sub>3</sub>, cycloocta-1,5-dienyliridium(I) 1,1,1,5,5,5-hexafluoropentane-2,4-dionate) were added to the reaction mixture in addition to the acid component. The preparative synthesis of [D]dopaquine was carried out by isotope exchange with deuterated water (D<sub>2</sub>O : TFA 5 : 1, 80°С, 3 h). [D]Dopaquine was obtained in 20% yield with the deuterium content in the interval 1.2–1.4 atoms per molecule. The deuterium content in the dopamine fragment is 1.2–1.3 atoms per molecule. The quinone fragment contained approximately 4–7% of the isotope.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 6","pages":"876 - 881"},"PeriodicalIF":0.9,"publicationDate":"2025-02-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143430962","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}
引用次数: 0
A Mathematical Model of the Removable Small-Size Melter Designed by the Mayak Production Association
IF 0.9
Radiochemistry Pub Date : 2025-02-17 DOI: 10.1134/S1066362224060158
E. I. Pon’kin, S. M. Shaydullin, V. A. Dudkin
{"title":"A Mathematical Model of the Removable Small-Size Melter Designed by the Mayak Production Association","authors":"E. I. Pon’kin,&nbsp;S. M. Shaydullin,&nbsp;V. A. Dudkin","doi":"10.1134/S1066362224060158","DOIUrl":"10.1134/S1066362224060158","url":null,"abstract":"<p>A digital model was developed and used for simulating the discharge of a borosilicate glass melt via the inductively heated drain of the removable small-size heater designed by the Mayak Production Association. The thermal calculation of the small-size furnace for high-level waste vitrification with borosilicate glass in the course of glass melting and discharge was made, and the calculation results were compared to the experimental data. The maximal difference in the absolute values of the temperature of furnace parts in the places of the thermocouple installation does not exceed 100°С, which corresponds to approximately 10% of the acting temperatures. Taking into account the assumptions made, this result can be considered satisfactory.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 6","pages":"901 - 909"},"PeriodicalIF":0.9,"publicationDate":"2025-02-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143430998","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}
引用次数: 0
Development and Implementation of a Technology for Tangential Filtration of Mother Liquors from Ammonia Precipitation of Uranium
IF 0.9
Radiochemistry Pub Date : 2025-02-17 DOI: 10.1134/S1066362224060109
N. S. Samarina, A. B. Melent’ev, A. V. Litvinov, Yu. A. Voroshilov, A. V. Konnikov, S. A. Lukin, M. V. Logunov, V. V. Milyutin
{"title":"Development and Implementation of a Technology for Tangential Filtration of Mother Liquors from Ammonia Precipitation of Uranium","authors":"N. S. Samarina,&nbsp;A. B. Melent’ev,&nbsp;A. V. Litvinov,&nbsp;Yu. A. Voroshilov,&nbsp;A. V. Konnikov,&nbsp;S. A. Lukin,&nbsp;M. V. Logunov,&nbsp;V. V. Milyutin","doi":"10.1134/S1066362224060109","DOIUrl":"10.1134/S1066362224060109","url":null,"abstract":"<p>The results of the development and implementation of a tangential filtration procedure for the treatment of mother liquors from ammonia precipitation of uranium are presented. The tangential filtration installation at RT-1 plant was put into operation in 2019. The productive capacity of the installation with respect to permeate is 450 dm<sup>3</sup>/h on the average. Up to 50 m<sup>3</sup> of the mother liquor can be processed in one filtration cycle. The decontamination factor is 10<sup>3</sup> for α-emitters and 10<sup>2</sup> to 10<sup>3</sup> for β-emitters. The resulting permeate corresponds in its activity to the LLW category.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 6","pages":"858 - 868"},"PeriodicalIF":0.9,"publicationDate":"2025-02-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143430999","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}
引用次数: 0
Determination of the Radionuclide Composition of the Cesium–Strontium Fraction of High-Level Waste from Spent Nuclear Fuel Reprocessing
IF 0.9
Radiochemistry Pub Date : 2025-02-17 DOI: 10.1134/S1066362224060146
E. V. Chukhlantseva, O. V. Stepanova, O. Yu. Dichenko, O. A. Kutuzova, K. A. Dzhevello, Yu. M. Tatarnikova, E. A. Demchenko, V. P. Borisenko
{"title":"Determination of the Radionuclide Composition of the Cesium–Strontium Fraction of High-Level Waste from Spent Nuclear Fuel Reprocessing","authors":"E. V. Chukhlantseva,&nbsp;O. V. Stepanova,&nbsp;O. Yu. Dichenko,&nbsp;O. A. Kutuzova,&nbsp;K. A. Dzhevello,&nbsp;Yu. M. Tatarnikova,&nbsp;E. A. Demchenko,&nbsp;V. P. Borisenko","doi":"10.1134/S1066362224060146","DOIUrl":"10.1134/S1066362224060146","url":null,"abstract":"<p>Procedures were developed for measuring and calculating the radionuclide composition of the cesium–strontium fraction of radioactive waste from spent nuclear fuel reprocessing. The optimum conditions for recovering specific components and separating them from components interfering with their determination were found. The content of the following controlled radionuclides was determined experimentally: <sup>14</sup>С, <sup>90</sup>Sr, <sup>99</sup>Tc, <sup>126</sup>Sn, <sup>129</sup>I, <sup>135,137</sup>Cs, <sup>234–236,238</sup>U, <sup>238–242</sup>Pu, <sup>237</sup>Np, <sup>241,243</sup>Am, and <sup>244–246</sup>Cm. The content of <sup>63</sup>Ni, <sup>93</sup>Zr, <sup>94</sup>Nb, <sup>151</sup>Sm, and <sup>242<i>m</i></sup>Am was determined by calculations. The radionuclide composition was determined in the solution before solidification of the cesium–strontium fraction. The composition of the solidified cesium–strontium fraction in the form of the borosilicate glass was determined by the calculation from the activity concentrations of the radionuclides in the solution before solidification and process characteristics (solution volume, glass frit weight, separation factors, and factors of incorporation into the glass).</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 6","pages":"890 - 900"},"PeriodicalIF":0.9,"publicationDate":"2025-02-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143430964","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}
引用次数: 0
Effect of Elevated Temperatures on the Dehydration of Radioactive Cement-Based Waste Forms Including Iron Hydroxide Slurries Containing α-Emitters
IF 0.9
Radiochemistry Pub Date : 2025-02-17 DOI: 10.1134/S106636222406016X
V. A. Remizova, P. A. Bobrov
{"title":"Effect of Elevated Temperatures on the Dehydration of Radioactive Cement-Based Waste Forms Including Iron Hydroxide Slurries Containing α-Emitters","authors":"V. A. Remizova,&nbsp;P. A. Bobrov","doi":"10.1134/S106636222406016X","DOIUrl":"10.1134/S106636222406016X","url":null,"abstract":"<p>The mechanical strength and chemical stability of the radioactive cement waste forms obtained by solidification of iron hydroxide slurries containing α-emitters were assessed with the aim to evaluate the effect of elevated temperatures in the range from 150 to 250°С. The dehydration of the waste forms in this temperature range exerts no significant negative effect on the extent of fixation of the radionuclides in the matrices and on the strength characteristics of the waste forms. The water loss on heating to 150°C is 11–13%, and further heating to 250°С leads to no more than 10% additional water loss.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 6","pages":"910 - 917"},"PeriodicalIF":0.9,"publicationDate":"2025-02-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143430959","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}
引用次数: 0
Solidification of the Strip Solution with Cesium-137 Using Porous Inorganic Material “Gubka”
IF 0.9
Radiochemistry Pub Date : 2025-02-17 DOI: 10.1134/S1066362224060092
A. S. Aloy, A. N. Vizniy, T. I. Koltsova, D. N. Shishkin
{"title":"Solidification of the Strip Solution with Cesium-137 Using Porous Inorganic Material “Gubka”","authors":"A. S. Aloy,&nbsp;A. N. Vizniy,&nbsp;T. I. Koltsova,&nbsp;D. N. Shishkin","doi":"10.1134/S1066362224060092","DOIUrl":"10.1134/S1066362224060092","url":null,"abstract":"<p>At the Khlopin Radium Institute, during the development of extractive partitioning of the liquid high-level radioactive waste (HLW), a strip solution containing up to 6.0 × 10<sup>11</sup> Bq/dm<sup>3</sup> (16.3 Ci/dm<sup>3</sup>) of <sup>137</sup>Cs in the form of a nitric acid solution was collected and temporary was stored. To solidify this solution, a batch process using Gubka (sponge) porous inorganic material (PIM) was developed and implemented. Since that time, about 18 dm<sup>3</sup> of HLW was solidified into 12 sets of Gubka, reducing the liquid HLW volume by a factor of about 50. Gubka sets were placed into special containers, which after sealing by welding were delivered to the long-time storage of the RosRAO Branch in Sosnovy Bor.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 6","pages":"852 - 857"},"PeriodicalIF":0.9,"publicationDate":"2025-02-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143431007","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}
引用次数: 0
High-Entropy Melt of Lithium, Sodium, and Potassium Fluorides and Chlorides as a Possible Coolant for Molten-Salt Reactors
IF 0.9
Radiochemistry Pub Date : 2025-02-17 DOI: 10.1134/S1066362224060031
D. O. Zakiryanov, N. K. Tkachev
{"title":"High-Entropy Melt of Lithium, Sodium, and Potassium Fluorides and Chlorides as a Possible Coolant for Molten-Salt Reactors","authors":"D. O. Zakiryanov,&nbsp;N. K. Tkachev","doi":"10.1134/S1066362224060031","DOIUrl":"10.1134/S1066362224060031","url":null,"abstract":"<p>Suggestions are made for potentially promising coolants for molten salt reactors from a mixture of six lithium, sodium, and potassium fluoride and chloride salts having high entropy of mixing. These compositions, which contain less lithium salts, should have higher thermodynamic stability than FLiNaK or FLiBe because of their high entropy. The chemical formula of the maximum high-entropy solution, Li<sub>1/6</sub>Na<sub>1/6</sub>K<sub>1/6</sub>F<sub>1/4</sub>Cl<sub>1/4</sub>, may result from mixing the variety of alkali halides like MX (M = Li, Na, K and X = F, Cl) taken in an equimolar ratio. Molecular dynamic estimations of the density, heat conductivity, and viscosity demonstrate reasonable values of these properties between those of the fluorides and chlorides.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 6","pages":"805 - 809"},"PeriodicalIF":0.9,"publicationDate":"2025-02-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143430909","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}
引用次数: 0
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