Radiochimica Acta最新文献

{"title":"Observations regarding the synthesis and redox chemistry of heterobimetallic uranyl complexes containing Group 10 metals","authors":"Emily R. Mikeska, Natalie M. Lind, Alexander C. Ervin, Celine Khalife, Joseph P. Karnes, James D. Blakemore","doi":"10.1515/ract-2023-0237","DOIUrl":"https://doi.org/10.1515/ract-2023-0237","url":null,"abstract":"Literature reports have demonstrated that Schiff-base-type ligands can serve as robust platforms for the synthesis of heterobimetallic complexes containing transition metals and the uranyl dication (UO<jats:sub>2</jats:sub> <jats:sup>2+</jats:sup>). However, efforts have not advanced to include either synthesis of complexes containing second- or third-row transition metals or measurement of the redox properties of the corresponding heterobimetallic complexes, despite the significance of actinide redox in studies of nuclear fuel reprocessing and separations. Here, metalloligands denoted [Ni], [Pd], and [Pt] that contain the corresponding Group 10 metals have been prepared and a synthetic strategy to access species incorporating the uranyl ion (UO<jats:sub>2</jats:sub> <jats:sup>2+</jats:sup>) has been explored, toward the goal of understanding how the secondary metals could tune uranium-centered redox chemistry. The synthesis and redox characterization of the bimetallic complex [Ni,UO<jats:sub>2</jats:sub>] was achieved, and factors that appear to govern extension of the chosen synthetic strategy to complexes with Pd and Pt are reported here. Infrared and solid-state structural data from X-ray diffraction analysis of the metalloligands [Pd] and [Pt] show that the metal centers in these complexes adopt the expected square planar geometries, while the structure of the bimetallic [Ni,UO<jats:sub>2</jats:sub>] reveals that the uranyl moiety influences the coordination environment of Ni(II), including inducement of a puckering of the ligand backbone of the complex in which the phenyl rings fold around the nickel-containing core in an umbrella-shaped fashion. Cyclic voltammetric data collected on the heterobimetallic complexes of both Ni(II) and Pd(II) provide evidence for uranium-centered redox cycling, as well as for the accessibility of other reductions that could be associated with Ni(II) or the organic ligand backbone. Taken together, these results highlight the unique redox behaviors that can be observed in multimetallic systems and design concepts that could be useful for accessing tunable multimetallic complexes containing the uranyl dication.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"16 1","pages":""},"PeriodicalIF":1.8,"publicationDate":"2024-02-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139759124","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":"Incorporation of phytic acid into reed straw-derived hydrochar for highly efficient and selective adsorption of uranium(VI)","authors":"Hongtao Xia, Yuting Liu, Yang Wang, Zihao Feng, Qi Ren, Jianqi Lv, Yang Li, Yanjun Du, Yun Wang","doi":"10.1515/ract-2023-0250","DOIUrl":"https://doi.org/10.1515/ract-2023-0250","url":null,"abstract":"An innovative phytic acid modified reed straw-derived hydrochar composite (PA-C-RBC) was prepared by using inexpensive reed straw and non-toxic phytic acid for the removal of uranium(VI) from aqueous environment. Several characterization results showed that PA-C-RBC was rough and porous with a large number of hydroxyl, carboxyl, and phosphate groups. The uranium(VI) adsorption process by PA-C-RBC conformed to pseudo-second-order kinetic and Langmuir models, and the theoretical maximal adsorption capacity could attain 418.78 mg/g at pH 5.0. PA-C-RBC had 72.66 % of selectivity and 6772.99 mL/g of distribution coefficient for U(VI). Due to the strong chelating between the hydroxyl and phosphate groups on PA-C-RBC and U(VI), PA-C-RBC had excellent adsorption selectivity. These finding highlighted a high potential for removing U(VI) from aqueous solutions.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"37 1","pages":""},"PeriodicalIF":1.8,"publicationDate":"2024-02-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139759130","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":"Characterization of glass composite material by pressureless sintering of soil and its application to uranium contaminated soil as a waste form","authors":"Jaewoong Hwang, Jaseung Koo, Kenyoung Lee","doi":"10.1515/ract-2023-0222","DOIUrl":"https://doi.org/10.1515/ract-2023-0222","url":null,"abstract":"When operating and dismantling a nuclear facility that handles uranium, the surrounding soil may be contaminated, emphasizing the need for appropriate treatment and disposal methods for soil waste. This study assessed high-temperature sintering technology for uranium contaminated soil waste to overcome limitations in existing decontamination methods and the volume increase associated with current solidification technology. The sintering process was found to effectively vitrify and re-mineralize complex chemical components in the soil. Sintered bodies were produced under varying conditions, adjusting molding pressure, heating temperature, and time. Optimized conditions resulted in sintered bodies with a volume reduction rate exceeding 30 % and a compressive strength surpassing 10 MPa, indicating a significant impact on the phase conversion and re-mineralization of silt and clay minerals. The soil sintering mechanism was identified through comprehensive microscopic observations and mineral phase change analysis. Leaching evaluations of sintered bodies, made from simulated uranium-contaminated soil, demonstrated their applicability to contaminated soil wastes. Additionally, it was confirmed that the sintering temperature of the soil could be lowered by incorporating a small amount of B<jats:sub>2</jats:sub>O<jats:sub>3</jats:sub>, suggesting a means to enhance the economic feasibility of the treatment process. The findings of this study highlight the applicability of pressureless sintering technology, based on glass composite materials, capable of simultaneously reducing and stabilizing uranium-contaminated soil waste.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"5 1","pages":""},"PeriodicalIF":1.8,"publicationDate":"2024-01-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139559238","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 radionuclides and heavy metal concentrations in the groundwater and adjacent areas of the Kattakurgan reservoir, Uzbekistan","authors":"U. Tukhtaev, Shakhboz Khasanov, Jaloliddin Fayzullayev, A. Safarov, Bayramali Togaev, Seyedkarim Afsharipour","doi":"10.1515/ract-2023-0254","DOIUrl":"https://doi.org/10.1515/ract-2023-0254","url":null,"abstract":"Abstract We conducted a comprehensive assessment of the Kattakurgan reservoir, alongside adjacent wells and boreholes, to measure the concentrations of natural radionuclides, heavy metals, and associated radiological hazards. Using NaI(Tl) crystal scintillation gamma spectrometers, we determined radionuclide levels in water and sediment. Inductively coupled plasma mass spectrometry (ICP-MS) was employed for heavy metal analysis. Our results showed radionuclide concentrations in reservoir water for 226Ra (0.8 Bq/L), 232Th (0.4 Bq/L), and 40K (0.4 Bq/L) were within the limits set by the World Health Organization (WHO). In contrast, deep well water samples showed elevated 226Ra concentrations (1.5 Bq/L). Sediment samples’ radionuclide levels were in line with UNSCEAR guidelines. Barium was the most notable heavy metal, with a concentration of 68.08 μg/L. While most radiation hazard indices remained within safety limits, the gamma index recorded a value of 1.057 Bq/kg. Our research provides valuable data for water quality assessment. The methods described can be applied to other reservoir studies. Regular monitoring is recommended for continuous safety evaluation, and further studies on biotic samples are suggested to enhance understanding of the reservoir’s ecosystem health.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"14 11","pages":""},"PeriodicalIF":1.8,"publicationDate":"2024-01-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139437313","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":"CaO-enhanced polyester for safety: experimental study on fabrication, characterization, and gamma-ray attenuation","authors":"M. Marashdeh, K. A. Mahmoud","doi":"10.1515/ract-2023-0265","DOIUrl":"https://doi.org/10.1515/ract-2023-0265","url":null,"abstract":"Abstract The current work deals with studying the influence of cheap, widespread CaO on improving the γ ray-protection capacity of the lightweight, sealing polyester. Therefore, polyester composites were filled with different concentrations of CaO fillers. The fabricated CaO-reinforced polyester composites’ density ranged between 1.177 g/cm3 and 1.377 g/cm3, when CaO filler concentrations increased between 0 wt% and 60 wt%, respectively. Fabricated composites’ morphology and chemical composition, as well as CaO fillers’ grain size and distribution, were proved using SEM and EDX spectroscopy. Additionally, the influence of CaO fillers on the gamma-ray shielding properties of the fabricated composites was evaluated using the Monte Carlo simulation and confirmed using the experimental measurements. The recorded results show an enhancement in the synthesized composites’ linear attenuation coefficient from 0.091 cm−1 to 0.106 cm−1 at a gamma ray energy of 0.662 MeV. Moreover, the excess in CaO concentration from 0 wt% and 60 wt% reduces the fabricated composites’ half-value thickness values from 7.64 cm to 6.51 cm, respectively.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"12 18","pages":""},"PeriodicalIF":1.8,"publicationDate":"2024-01-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139437728","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":"Overcoming the obstacle of excess acetonitrile content in the final fluorine-18 radiotracers","authors":"Mohammed Al-Qahtani","doi":"10.1515/ract-2023-0225","DOIUrl":"https://doi.org/10.1515/ract-2023-0225","url":null,"abstract":"Abstract Acetonitrile is widely used as a solvent in synthesizing various fluorine-18 positron emission tomography (PET) radiotracers. Acetonitrile is classified as a Class II residual solvent, and due to its inherent toxic properties, the quantity of residual acetonitrile in drug products has to be limited. When working under Good Manufacturing Practices (GMP) during the radiosynthesis of a radiotracer, the aim is to control all solvent concentrations contained in the ready-to-use product. All products must meet predetermined specifications. Rarely, these limits may be exceeded. To avoid eliminating the entire batch, applying a straightforward time-based technique would be desirable to allow the majority of the product to be safely used. This technique should be based on determining a specific time and volume for which the radiotracer can be utilized in the patients after completing quality control analysis. Here, we report a very simple Excel sheet program based on existing mathematical equations that calculates the exact time and volume at which the radiotracer product can be safely administered to a patient.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"44 8","pages":""},"PeriodicalIF":1.8,"publicationDate":"2024-01-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139379866","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":"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":"44 1","pages":""},"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":"5 1","pages":""},"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":"110 1","pages":""},"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":"19 1","pages":""},"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}