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Reaction of Nitrate Ion with Formic Acid in the Presence of Uranium 硝酸离子与甲酸在铀存在下的反应
IF 0.9
Radiochemistry Pub Date : 2025-04-05 DOI: 10.1134/S1066362225010023
L. V. Krasnikov, A. A. Lumpov, N. A. Semenova
{"title":"Reaction of Nitrate Ion with Formic Acid in the Presence of Uranium","authors":"L. V. Krasnikov,&nbsp;A. A. Lumpov,&nbsp;N. A. Semenova","doi":"10.1134/S1066362225010023","DOIUrl":"10.1134/S1066362225010023","url":null,"abstract":"<p>The reaction of nitric acid with formic acid, including that in uranium-containing solutions, was studied. Empirical equations for the dependence of the induction period (τ) on the reactant concentrations and temperature were determined. The dependence of τ on the formic acid concentration is exponential. The effect of uranium concentration on τ in denitrated solutions becomes noticeable only at temperatures lower than 60°C. The main factor affecting the denitration completeness is the [formic acid] : [NO<sub>3</sub>]¯ molar ratio. Starting from the molar ratio of ≥3, uranium-containing solutions are denitrated at 90°C in an hour almost quantitatively. The resulting uranyl formate is partially precipitated. The initial stage of the reaction is accompanied by vigorous gas evolution. At 90°C, ~80% of the gas volume is released in this stage (about 10 s), whereas at 40°C, only ~10%.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"67 1","pages":"8 - 14"},"PeriodicalIF":0.9,"publicationDate":"2025-04-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143784158","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
Modeling of the Composition of the Gas Phase over Uranium–Plutonium Mononitride Containing Oxygen Impurities and Fission Products 含氧杂质铀-钚单氮和裂变产物气相组成的建模
IF 0.9
Radiochemistry Pub Date : 2025-04-05 DOI: 10.1134/S1066362225010059
G. S. Bulatov, K. E. German
{"title":"Modeling of the Composition of the Gas Phase over Uranium–Plutonium Mononitride Containing Oxygen Impurities and Fission Products","authors":"G. S. Bulatov,&nbsp;K. E. German","doi":"10.1134/S1066362225010059","DOIUrl":"10.1134/S1066362225010059","url":null,"abstract":"<p>The composition of the gas phase over uranium–plutonium nitride U<sub>0.8</sub>Pu<sub>0.2</sub>N<sub>0.995</sub>0<sub>0.005</sub> containing oxygen impurities and fission products after fast neutron irradiation to a burnup of 13.6% heavy atoms (h.a.) was subjected to a thermodynamic analysis in the temperature interval 900–2000 K. In this interval, the accumulation of fission products in the fuel leads to the formation of a multicomponent gas phase containing the following main elements and compounds: fuel species (Pu, PuO, PuN, U, UO, UN), highly volatile species (Cs, N<sub>2</sub>, Ba, Sr, CsI, BaI, SrI, I), volatile species (Te, Pd, BaO, NdO, LaO, SrO, CeO), low-volatile metals (Nd, Mo, Y, Tc, La, Ce, Zr), and low-volatile nitrides (NdN, LaN, CeN, YN, ZrN). The partial pressures of these components of the gas phase over U<sub>0.8</sub>Pu<sub>0.2</sub>N<sub>0.995</sub>0<sub>0.005</sub> at the 13.6% burnup as functions of temperature were calculated.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"67 1","pages":"31 - 38"},"PeriodicalIF":0.9,"publicationDate":"2025-04-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143784152","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 Conditions for the Oxidation of UN and UC under Microwave Irradiation 微波辐照下UN和UC氧化条件的测定
IF 0.9
Radiochemistry Pub Date : 2025-04-05 DOI: 10.1134/S1066362225010011
S. A. Kulyukhin, Yu. M. Nevolin, A. A. Bessonov
{"title":"Determination of Conditions for the Oxidation of UN and UC under Microwave Irradiation","authors":"S. A. Kulyukhin,&nbsp;Yu. M. Nevolin,&nbsp;A. A. Bessonov","doi":"10.1134/S1066362225010011","DOIUrl":"10.1134/S1066362225010011","url":null,"abstract":"<p>The oxidation of UN and UC in a field of microwave radiation in air at atmospheric pressure was studied. The influence of the crucible material on the extent of oxidation of UN and UC was examined. Under the influence of a microwave field with a power of 800 W and a frequency of 2.45 GHz, under definite conditions, heating of UN and UC to ~993 K is observed with their oxidation in air to U<sub>3</sub>O<sub>8</sub>. For fast (15–20 min) and safe (without fires and explosions) oxidation of UN and UC, crucibles made of quartz and carbon ceramics are the best.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"67 1","pages":"1 - 7"},"PeriodicalIF":0.9,"publicationDate":"2025-04-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143784157","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
Joint Solubility of Uranyl(VI) and Plutonyl(VI) Nitrates in Nitric Acid Solutions 硝酸溶液中铀酰（VI）和硝酸钚酰（VI）的联合溶解度
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
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 多巴喹的氘标记
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 玛雅克生产协会设计的可移动小尺寸熔炼机的数学模型
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 铀氨沉淀母液切向过滤技术的开发与实现
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 乏核燃料后处理高放废物铯锶组分放射性核素组成的测定
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
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