Radiochimica Acta最新文献

{"title":"Morphology of uranium oxides reduced from magnesium and sodium diuranate","authors":"Aaron M. Chalifoux, Logan Gibb, Kimberly N. Wurth, Travis Tenner, Tolga Tasdizen, Luther W. McDonald","doi":"10.1515/ract-2023-0221","DOIUrl":"https://doi.org/10.1515/ract-2023-0221","url":null,"abstract":"Morphological analysis of uranium materials has proven to be a key signature for nuclear forensic purposes. This study examines the morphological changes to magnesium diuranate (MDU) and sodium diuranate (SDU) during reduction in a 10 % hydrogen atmosphere with and without steam present. Impurity concentrations of the materials were also examined pre and post reduction using energy dispersive X-ray spectroscopy combined with scanning electron microscopy (SEM-EDX). The structures of the MDU, SDU, and UO<jats:sub> <jats:italic>x</jats:italic> </jats:sub> samples were analyzed using powder X-ray diffraction (p-XRD). Using this method, UO<jats:sub> <jats:italic>x</jats:italic> </jats:sub> from MDU was found to be a mixture of UO<jats:sub>2</jats:sub>, U<jats:sub>4</jats:sub>O<jats:sub>9</jats:sub>, and MgU<jats:sub>2</jats:sub>O<jats:sub>6</jats:sub> while UO<jats:sub> <jats:italic>x</jats:italic> </jats:sub> from SDU were combinations of UO<jats:sub>2</jats:sub>, U<jats:sub>4</jats:sub>O<jats:sub>9</jats:sub>, U<jats:sub>3</jats:sub>O<jats:sub>8</jats:sub>, and UO<jats:sub>3</jats:sub>. By SEM, the MDU and UO<jats:sub> <jats:italic>x</jats:italic> </jats:sub> from MDU had identical morphologies comprised of large agglomerates of rounded particles in an irregular pattern. SEM-EDX revealed pockets of high U and high Mg content distributed throughout the materials. The SDU and UO<jats:sub> <jats:italic>x</jats:italic> </jats:sub> from SDU had slightly different morphologies. The SDU consisted of massive agglomerates of platy sheets with rough surfaces. The UO<jats:sub> <jats:italic>x</jats:italic> </jats:sub> from SDU was comprised of massive agglomerates of acicular and sub-rounded particles that appeared slightly sintered. Backscatter images of SDU and related UO<jats:sub> <jats:italic>x</jats:italic> </jats:sub> materials showed sub-rounded dark spots indicating areas of high Na content, especially in UO<jats:sub> <jats:italic>x</jats:italic> </jats:sub> materials created in the presence of steam. SEM-EDX confirmed the presence of high sodium concentration spots in the SDU and UO<jats:sub> <jats:italic>x</jats:italic> </jats:sub> from SDU. Elemental compositions were found to not change between pre and post reduction of MDU and SDU indicating that reduction with or without steam does not affect Mg or Na concentrations. The identification of Mg and Na impurities using SEM analysis presents a readily accessible tool in nuclear material analysis with high Mg and Na impurities likely indicating processing via MDU or SDU, respectively. Machine learning using convolutional neural networks (CNNs) found that the MDU and SDU had unique morphologies compared to previous publications and that there are distinguishing features between materials created with and without steam.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2023-12-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139053549","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Radioactivity of 226Ra, 232Th and 40K in soil in Northwest part of Turkey: assessment of radiological impacts","authors":"Selin Özden","doi":"10.1515/ract-2023-0219","DOIUrl":"https://doi.org/10.1515/ract-2023-0219","url":null,"abstract":"The surface soil samples were collected from Northwest Turkey. The activity concentrations of <jats:sup>226</jats:sup>Ra, <jats:sup>232</jats:sup>Th, and <jats:sup>40</jats:sup>K were measured using an HPGe gamma-spectroscopy system. The activity concentrations of <jats:sup>226</jats:sup>Ra, <jats:sup>232</jats:sup>Th, and <jats:sup>40</jats:sup>K in the soils were found to be in the range of 11.78 ± 1.12–43.89 ± 14.94, 3.19 ± 2.01–88.22 ± 0.92, 362.81 ± 5.94–829.27 ± 12.38 Bq kg<jats:sup>−1</jats:sup> d.w., respectively. The Surfer program was used to obtain 3-dimensional maps of the specific activities. Radium Equivalent Activity (Ra<jats:sub>eq</jats:sub>), Absorbed Gamma Dose Rate (<jats:italic>D</jats:italic>), Annual Effective Dose Equivalent (AEDE), The Excess Life Time Cancer Risk (ELCR), External (<jats:italic>H</jats:italic> <jats:sub>ex</jats:sub>) and Internal (<jats:italic>H</jats:italic> <jats:sub>in</jats:sub>) Hazard Indexes, Annual Gonadal Dose Equivalent (AGDE), and Activity Utilization Index (AUI) were calculated and compared with the recommended values. Pearson’s correlation analysis (PCA) and factor analysis (FA) were utilized to analyze the data and indicate between the radiological parameters. The analysis showed that the total radiation was mainly caused by <jats:sup>226</jats:sup>Ra and <jats:sup>232</jats:sup>Th.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2023-12-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138630784","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"HR GRS-HPGe as NDT method for quantification of uranium and U235 content in process stream samples from UO2 fuel production facilities","authors":"Yarasi Balaji Rao, Vinod K. Ray, Putta V. Nagendra Kumar, Dinesh Srivastava","doi":"10.1515/ract-2023-0186","DOIUrl":"https://doi.org/10.1515/ract-2023-0186","url":null,"abstract":"Uranium concentration and uranium isotopic content are two important and critical parameters for any nuclear fuel fabrication facilities. In the present study emphasis has been given on the usage of high resolution gamma ray spectrometric (HR-GRS) technique with HPGe detector for the determination of uranium and <jats:sup>235</jats:sup>U content in uranium process stream samples. The work has been carried out with an aim to give quick analytical feedback to production facility and also to minimize the generation of analytical waste. These are important requirements for any industrial lab with high analytical load attached to production facility. In this paper a simple and a non-destructive testing (NDT) method has been described for quantification of uranium and <jats:sup>235</jats:sup>U content in samples received from UO<jats:sub>2</jats:sub> fuel production facilities using HR-GRS technique with high purity germanium (HPGe) detector. A 185.7 keV line of <jats:sup>235</jats:sup>U has been used for quantification of uranium in process solutions containing 1 g/L to 600 g/L of uranium covering both aqueous and organic process stream solutions. The results have been compared with that of Davies and Gray method. The limitations associated with gamma ray emitted from daughter products of <jats:sup>238</jats:sup>U and self-induced or self-excited X-ray fluorescence lines of uranium have also been studied. Multi Group Analysis of Uranium (MGAU) software code has been used for measurement of <jats:sup>235</jats:sup>U content in variety of samples. The results obtained are compared with that of results by thermal ionization mass spectrometer (TIMS).","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2023-12-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138576755","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Gamma-radiation levels along the main Karakorum thrust area of Northern Pakistan","authors":"Mohammad Wasim, Arfan Tariq, Manzoor Ali","doi":"10.1515/ract-2023-0229","DOIUrl":"https://doi.org/10.1515/ract-2023-0229","url":null,"abstract":"In this contribution, the distribution of naturally occurring radionuclides in the area around Main Karakoram Thrust (MKT) in Karakoram Range, North Pakistan is documented. Three natural radionuclides (<jats:sup>226</jats:sup>Ra, <jats:sup>232</jats:sup>Th, and <jats:sup>40</jats:sup>K) and one anthropogenic radionuclide (<jats:sup>137</jats:sup>Cs) were studied for their specific activities in 30 samples. The measurements were made by high resolution gamma-ray spectrometry. The sampling area is located in Gilgit Baltistan province of Pakistan at an altitude of 1838 m/6030 ft above sea level. MKT separates the Karakoram plate from the Kohistan-Ladakh Terranes and Indian Plate to the south. The specific activity varied as 4.5–56.5 Bq kg<jats:sup>−1</jats:sup>, 18.2–61.4 Bq kg<jats:sup>−1</jats:sup>, 1.4–19.6 Bq kg<jats:sup>−1</jats:sup> and 51–1640 Bq kg<jats:sup>−1</jats:sup> for <jats:sup>226</jats:sup>Ra, <jats:sup>232</jats:sup>Th, <jats:sup>137</jats:sup>Cs and <jats:sup>40</jats:sup>K, respectively. The average radium equivalent activity was 127.8 ± 45.9 Bq kg<jats:sup>−1</jats:sup>. The external hazard index was &lt;1 for all samples and representative level index was &lt;1 for majority of the samples. The average air absorbed dose rate was 60.9 ± 23.2 nGy h<jats:sup>−1</jats:sup> corresponding to the outdoor effective dose rate of 73.7 ± 28.0 μSv y<jats:sup>−1</jats:sup>. These values were slightly higher than the world average values for air absorbed dose rate (51 nGy h<jats:sup>−1</jats:sup>) and outdoor annual effective dose rate (70 μSv y<jats:sup>−1</jats:sup>). The data revealed significant positive correlation between <jats:sup>226</jats:sup>Ra and <jats:sup>40</jats:sup>K. Principal component analysis revealed distribution patterns within the samples and identified three distinct groups. Data was also evaluated for the concentrations of uranium, thorium and potassium and their ratios.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2023-12-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138553158","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Determination of natural and artificial radioactivity levels and radiation hazard indices for soil samples in Kırşehir","authors":"Sümeyra Yamçıçıer, Doğan Yaşar","doi":"10.1515/ract-2023-0215","DOIUrl":"https://doi.org/10.1515/ract-2023-0215","url":null,"abstract":"The aim of this study is to create a radiological map of Kırşehir province in Turkey by analyzing the radioactivity levels of soil samples and environmental radiation measurements. <jats:sup>226</jats:sup>Ra, <jats:sup>232</jats:sup>Th, <jats:sup>40</jats:sup>K and <jats:sup>137</jats:sup>Cs radionuclides were analysed in soil samples collected from 47 locations using gamma spectrometry with an HPGe detector. According to the results obtained, gamma radioactivity concentration ranges and mean values for <jats:sup>226</jats:sup>Ra, <jats:sup>232</jats:sup>Th, <jats:sup>40</jats:sup>K and <jats:sup>137</jats:sup>Cs were determined as 133 ± 15–1515 ± 128 Bq/kg (599.40 Bq/kg), 0.3 ± 0.09–21.1 ± 1.7 Bq/kg (4.61 Bq/kg), 8.7 ± 0.9–128.5 ± 8.5 Bq/kg (29.66 Bq/kg) and 11.6 ± 8.6–273.8 ± 19.9 Bq/kg (48.80 Bq/kg) respectively. Average radioactivity levels for <jats:sup>40</jats:sup>K and <jats:sup>232</jats:sup>Th are above the world average. The mean radium equivalent activity (Ra<jats:sub>eq</jats:sub>), gamma dose rate (<jats:italic>D</jats:italic>), annual effective dose equivalent (AEDE), external hazard index (<jats:italic>H</jats:italic> <jats:sub> <jats:italic>ex</jats:italic> </jats:sub>), and the excess lifetime cancer risk (ELCR) were calculated as 145.45 Bq/kg, 122.13 nGy/h, 0.15 mSv/h, 0.39 and 0.29 × 10<jats:sup>−3</jats:sup> respectively.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2023-12-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138529146","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Recycling waste polymer packaging materials as effective active carbon porous materials for uranium removal from commercial phosphoric acid","authors":"Saber Ibrahim, Ahmed M. Masoud, Mahmoud M. El-Maadawy, Hager Fahmy, Mohamed Taha","doi":"10.1515/ract-2023-0165","DOIUrl":"https://doi.org/10.1515/ract-2023-0165","url":null,"abstract":"Plastic packaging waste is considered a serious threat to the environment due to its non-biodegradable nature. Transforming plastic waste into active carbons using pyrolysis methods could be a valuable option to solve the challenge of plastic waste. Synthesized active carbon was differentiated using zeta potential, particle size, SEM, BET, and DSC. This study also investigates the use of obtained active carbons for U(VI) removal from commercial phosphoric acid. The kinetics of adsorption were found to follow the pseudo-second-order model and intra-particle diffusion as one of the controlling mechanisms. Langmuir, and Freundlich, isotherms were employed to explore the equilibrium data. Furthermore, thermodynamic investigations revealed that uranium uptake is an endothermic, feasible, and spontaneous process. The present study concludes that plastic waste-based activated carbon could be employed as a low-cost alternative to commercial activated carbon for uranium removal from phosphoric acid and the production of green fertilizers.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2023-11-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138529110","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Inorganic composites based on carboxymethyl cellulose: preparation, characterization, sorption, and selectivity behavior for some radionuclides from radioactive solutions","authors":"Mohamed Ragab Abass, Maha Ali Youssef, Marwa Ahmed Eid","doi":"10.1515/ract-2023-0214","DOIUrl":"https://doi.org/10.1515/ract-2023-0214","url":null,"abstract":"This work is interested in the sorption and separation of <jats:sup>131</jats:sup>Ba, <jats:sup>109</jats:sup>Cd, <jats:sup>152+154</jats:sup>Eu, and <jats:sup>97</jats:sup>Zr from radioactive solutions onto barium molybdenum titanate loaded on carboxy methyl cellulose (BaMoTi@CMC) composites. In this work, different samples of BaMoTi@CMC composites were fabricated by the co-precipitation method and characterized using different analytical tools such as X-ray diffraction (XRD), attenuated total reflectance (ATR), and scanning electron microscope (SEM). The batch sorption investigations on <jats:sup>131</jats:sup>Ba, <jats:sup>109</jats:sup>Cd, <jats:sup>152+154</jats:sup>Eu, and <jats:sup>97</jats:sup>Zr include the influence of time, pH, and metal ion concentrations. The data reveal that S-3 has higher sorption efficiency than S-2 under all conditions. Isotherm is studied by Langmuir and Freundlich models. Binary systems data confirm that Cd(<jats:sc>ii</jats:sc>), Ba(<jats:sc>ii</jats:sc>), and Zr(<jats:sc>iv</jats:sc>) can be separated from Cd–Eu, Ba–Eu, and Zr–Eu binary systems using S-2 and S-3 at different pHs. Finally, the data prove that Zr(<jats:sc>iv</jats:sc>) and Ba(<jats:sc>ii</jats:sc>) can be easily separated from tertiary systems (Zr–Ba–Cd) onto S-2 and S-3 at pH 2.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2023-11-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138529138","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Production of Auger-electron-emitting 103mRh via a 103Pd/103mRh generator using an anion-exchange resin","authors":"Tomoyuki Ohya, Jun Ichinose, Kotaro Nagatsu, Yumi Sugo, Noriko Ishioka, Hiroshi Watabe, Masatoshi Itoh, Katsuyuki Minegishi, Ming-Rong Zhang","doi":"10.1515/ract-2023-0238","DOIUrl":"https://doi.org/10.1515/ract-2023-0238","url":null,"abstract":"Rhodium-103m is one of the most attractive Auger electron emitters for internal radiotherapy. The half-life of <jats:sup>103m</jats:sup>Rh is relatively short (56.114 min). Therefore, it needs to be produced using a generator for clinical use. Most studies of <jats:sup>103</jats:sup>Pd/<jats:sup>103m</jats:sup>Rh generators using anion-exchange resins were carried out over 50 years ago. However, these resins are no longer commercially available. In the present study, we tested a <jats:sup>103</jats:sup>Pd/<jats:sup>103m</jats:sup>Rh generator using alternative anion-exchange resins (i.e., IRA904, IRA410, SA20A, and SA11AL). No-carrier-added <jats:sup>103</jats:sup>Pd was used to make the generators. The <jats:sup>103m</jats:sup>Rh product was eluted from the generators using 6 mL of 0.1 M HCl with a flow rate 0.5 mL/min. The generator made from SA11AL showed good performance, with a yield of 39 %, an impurity level of <jats:sup>103</jats:sup>Pd in the product of 0.29 %, and an operation time of 14 min. This makes this generator competitive with previously developed ones.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2023-11-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138529149","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Efficient removal of U(VI) from aqueous solution by hydroxyapatite/graphene oxide composite microspheres","authors":"Wenjun Wu, Jianlong Wang","doi":"10.1515/ract-2023-0235","DOIUrl":"https://doi.org/10.1515/ract-2023-0235","url":null,"abstract":"Effective treatment of uranium-containing wastewater is of great significance to the sustainable development of nuclear power and the protection of ecological environment. In this study, a highly efficient uranium adsorbent, graphene oxide (GO)/nano-hydroxyapatite (nHA) composite microspheres (nHA@rGO) was synthesized, which could effectively remove uranium from aqueous solution. Under the condition of pH = 3.5, <jats:italic>T</jats:italic> = 298 K, the maximum adsorption capacity reached 1672.96 mg/g. The results of batch experiments showed that the adsorption capacity of nHA@rGO microspheres was higher than that of nHA microspheres, indicating the enhancement of GO. The adsorption kinetics conformed to the pseudo second-order model. The changes of nHA@rGO microspheres before and after uranium adsorption were analyzed by FT-IR, XPS and XRD. The mechanisms of U(VI) ions adsorption onto nHA@rGO microspheres involved precipitation, surface complexation and ion exchange, in which the hydroxyl and phosphoric acid groups played important roles. The results showed that the prepared nHA@rGO microspheres can be used as an efficient and promising adsorbent for the treatment of uranium-containing wastewater.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2023-11-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138529137","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Studies on the acidification of carbonate waste stream for separation of di-butyl phosphate and recovery of metal","authors":"Satyabrata Mishra, Pankaj, Chayan Patra, Debojyoti Ghosh, N. Desigan, P. Velavendan, K. A. Venkatesan, Ananthasivan Krishnamurthy","doi":"10.1515/ract-2023-0196","DOIUrl":"https://doi.org/10.1515/ract-2023-0196","url":null,"abstract":"Abstract The aqueous waste generated during the treatment of Purex lean organic phase with alkaline carbonate solution contains washable degradation products and actinides in the form of carbonate complex. Management of such aqueous waste demands quantitative removal of the main degradation product, dibutyl phosphate (HDBP) and actinides from aqueous solution. In this context, batch studies have been carried out on the separation of HDBP from aqueous solution using n-dodecane (n-DD). For this purpose, the extraction behaviour of HDBP in n-DD was studied after acidification of alkaline carbonate solution with nitric acid. The studies with simulated waste containing HDBP and U(VI) nitrate showed the loss of U(VI) as precipitate during acidification as the uranium–DBP was poorly soluble in aqueous phase. However, the loss of U(VI) decreased with increase of aqueous phase acidity showing that the adjusted acidity of the carbonate waste plays an important role in the recovery of actinides.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2023-11-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139267479","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}