Lingting Xia, Han Wu, Jing Gao, Tianzhen Ye, Long Qiu, Feize Li, Tu Lan, Jijun Yang, Jiali Liao, Ning Liu, Yuanyou Yang
In this work, a gallium–nickel alloy target with a weight percentage ratio of 7:3 was successfully prepared on Cu substrate in a chloride system at room temperature. A novel organic-solvent-free separation procedure based on two columns for extracting 68Ge from irradiated Ga–Ni alloy target with high radionuclidic purity (99.99 %) was developed. By this separation procedure, the recovery of 68Ge is 95 ± 5 % and the yield of 68Ge via the nuclear reaction natGa(p,xn)68Ge was measured to be 0.27 ± 0.02 MBq/μA h.
{"title":"Efficient extraction of 68Ge from irradiated Ga–Ni alloy via a novel organic-solvent-free separation procedure","authors":"Lingting Xia, Han Wu, Jing Gao, Tianzhen Ye, Long Qiu, Feize Li, Tu Lan, Jijun Yang, Jiali Liao, Ning Liu, Yuanyou Yang","doi":"10.1515/ract-2023-0161","DOIUrl":"https://doi.org/10.1515/ract-2023-0161","url":null,"abstract":"In this work, a gallium–nickel alloy target with a weight percentage ratio of 7:3 was successfully prepared on Cu substrate in a chloride system at room temperature. A novel organic-solvent-free separation procedure based on two columns for extracting <jats:sup>68</jats:sup>Ge from irradiated Ga–Ni alloy target with high radionuclidic purity (99.99 %) was developed. By this separation procedure, the recovery of <jats:sup>68</jats:sup>Ge is 95 ± 5 % and the yield of <jats:sup>68</jats:sup>Ge via the nuclear reaction <jats:sup>nat</jats:sup>Ga(p,<jats:italic>x</jats:italic>n)<jats:sup>68</jats:sup>Ge was measured to be 0.27 ± 0.02 MBq/μA h.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2023-11-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138529097","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}
Abstract This work focused the determination of the rare earth elements (REE) in Algerian bentonites named Mos and Mag using k 0 -NAA method. Eleven rare earth elements such as Ce, Nd, La, Sc, Sm, Yb, Tm, Ho, Tb, Eu and Lu were determined. Results revealed that the total light REE (LREE) in Mos (168 ppm) is higher than in Mag (68.5 ppm). In addition, the ratio of total LREE (LREE) to the total heavy rare earth elements (HREE) found to be 6.40 in Mag and 27.6 in Mos which indicates that Mos is highly rich with REE than Mag. Ce and Eu correspond to the highest and lower trace of REE in both bentonites, respectively. The concentration of Sc, Tb and Ho are comparable in two materials. All results are compared with other data of literature in terms of La, Sc, Ce, Nd, Sm and Yb. Amounts and the proportion of LREE comparing to THREE are discussed in this study.
{"title":"Determination of rare earth elements in Algerian bentonites using <i>k</i> <sub>0</sub>-NAA method","authors":"Lylia Hamidatou, Fahd Arbaoui, Radji Chahra, Hocine Slamene, Kamel Djebli, Mohamed Nadir Boucherit","doi":"10.1515/ract-2023-0210","DOIUrl":"https://doi.org/10.1515/ract-2023-0210","url":null,"abstract":"Abstract This work focused the determination of the rare earth elements (REE) in Algerian bentonites named Mos and Mag using k 0 -NAA method. Eleven rare earth elements such as Ce, Nd, La, Sc, Sm, Yb, Tm, Ho, Tb, Eu and Lu were determined. Results revealed that the total light REE (LREE) in Mos (168 ppm) is higher than in Mag (68.5 ppm). In addition, the ratio of total LREE (LREE) to the total heavy rare earth elements (HREE) found to be 6.40 in Mag and 27.6 in Mos which indicates that Mos is highly rich with REE than Mag. Ce and Eu correspond to the highest and lower trace of REE in both bentonites, respectively. The concentration of Sc, Tb and Ho are comparable in two materials. All results are compared with other data of literature in terms of La, Sc, Ce, Nd, Sm and Yb. Amounts and the proportion of LREE comparing to THREE are discussed in this study.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135431279","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}
Mohamed R. Abass, Sara S. Mahrous, Muhammad S. Mansy
Abstract Using batch and column procedures, the present work investigated the sorption behaviour of 137 Cs and 152+154 Eu by bentonite phosphate modified with nickel (BPN) sorbent. The kinetic data obey pseudo-1 st -order for 137 Cs and follow pseudo-2 nd -order for 152+154 Eu. Various sorption isotherm models were used to analyze equilibrium data. The thermodynamic functions reflect an endothermic and spontaneous sorption process. HCl (about 95.35 %) and CaCl 2 (about 98.13 %) showed the optimum eluents for the complete recovery of both 137 Cs and 152+154 Eu, respectively. Finally, column data show that 137 Cs and 152+154 Eu may be loaded on BNP sorbent and separated from an aqueous solution using a variety of HCl concentrations as eluent. The obtianed results revealed that BNP sorbent is suitable for recovering 137 Cs and 152+154 Eu from low-level radioactive waste effluents (LLW).
{"title":"Sorption behaviour of <sup>137</sup>Cs and <sup>152+154</sup>Eu onto bentonite phosphate modified with nickel: kinetics, isotherms, and chromatographic column application","authors":"Mohamed R. Abass, Sara S. Mahrous, Muhammad S. Mansy","doi":"10.1515/ract-2023-0168","DOIUrl":"https://doi.org/10.1515/ract-2023-0168","url":null,"abstract":"Abstract Using batch and column procedures, the present work investigated the sorption behaviour of 137 Cs and 152+154 Eu by bentonite phosphate modified with nickel (BPN) sorbent. The kinetic data obey pseudo-1 st -order for 137 Cs and follow pseudo-2 nd -order for 152+154 Eu. Various sorption isotherm models were used to analyze equilibrium data. The thermodynamic functions reflect an endothermic and spontaneous sorption process. HCl (about 95.35 %) and CaCl 2 (about 98.13 %) showed the optimum eluents for the complete recovery of both 137 Cs and 152+154 Eu, respectively. Finally, column data show that 137 Cs and 152+154 Eu may be loaded on BNP sorbent and separated from an aqueous solution using a variety of HCl concentrations as eluent. The obtianed results revealed that BNP sorbent is suitable for recovering 137 Cs and 152+154 Eu from low-level radioactive waste effluents (LLW).","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-11-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135777133","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}
Beatriz Acevedo, Karen Van Hecke, Thomas Cardinaels, Marc Verwerft
Abstract Space mission beyond the solar system cannot rely on photovoltaic (PV) cells as primary power source, and combinations of PV cells and batteries. For such purpose, Radioisotope Power Systems powered with 238 Pu have served well for all flagship space exploration missions since the early Apollo missions until today’s Mars Exploration Program and continue to be the preferred primary energy source for future missions. 238 Pu production proceeds via neutron irradiation of 237 Np, which is created as a by-product in nuclear fission reactors. Neutron irradiation of 237 Np to produce 238 Pu is conceptually very simple, but the production of sizeable quantities of 238 Pu with acceptable isotopic purity, and the further separation and processing stages pose formidable technological challenges. 238 Pu is a highly radiotoxic alpha emitter with an elevated specific activity and high decay energy with high risk for the workers, and its precursor, 237 Np, is a radiotoxic alpha emitter whose daughter 233 Pa decays to 233 U with a strong gamma emission. Furthermore, the very rich and weakly explored chemistry of Np is also a challenge. The historical 238 Pu inventory of US-DOE has been highly consumed and supplies of available 238 Pu to support new missions have diminished. NASA and US-DOE have started an extensive project to re-establish 238 Pu production for US space missions. In Europe, ESA has also shown some interest in an European production of 238 Pu for the European space missions. In the present review, the manufacture of Np targets for 238 Pu production by irradiation, and the target processing are discussed and assessed from an European production perspective by comparing mainly US state-of-the-art with the European know-how and the current facilities. Two principal options for target fabrication stand out: aluminium-clad NpO 2 –Al CERMET and zircaloy-clad full-ceramic NpO 2 targets. The principal advantages of the well documented CERMET route can be found in the irradiation stage. These targets allow a high flexibility in heavy metal loading fraction and have high thermal performance. But, they have significant drawbacks in terms of the amount and type of nuclear waste that is generated at the back-end. Instead, the full-ceramic targets are conceptually very similar to conventional nuclear fuels, and would be preferred from back-end perspective, although a demonstration of large scale production remains yet to be done. Presently, there are no operational large scale Np target production, irradiation, processing or 238 Pu handling facilities in Europe, but the nuclear infrastructure exists and is operational to study each of the steps at least at small scale and all steps have similarities with well-established industrial capabilities in Europe.
{"title":"<sup>238</sup>Pu production: a State-of-the-Art review of NpO<sub>2</sub> target fabrication technologies and processing of irradiated targets","authors":"Beatriz Acevedo, Karen Van Hecke, Thomas Cardinaels, Marc Verwerft","doi":"10.1515/ract-2023-0150","DOIUrl":"https://doi.org/10.1515/ract-2023-0150","url":null,"abstract":"Abstract Space mission beyond the solar system cannot rely on photovoltaic (PV) cells as primary power source, and combinations of PV cells and batteries. For such purpose, Radioisotope Power Systems powered with 238 Pu have served well for all flagship space exploration missions since the early Apollo missions until today’s Mars Exploration Program and continue to be the preferred primary energy source for future missions. 238 Pu production proceeds via neutron irradiation of 237 Np, which is created as a by-product in nuclear fission reactors. Neutron irradiation of 237 Np to produce 238 Pu is conceptually very simple, but the production of sizeable quantities of 238 Pu with acceptable isotopic purity, and the further separation and processing stages pose formidable technological challenges. 238 Pu is a highly radiotoxic alpha emitter with an elevated specific activity and high decay energy with high risk for the workers, and its precursor, 237 Np, is a radiotoxic alpha emitter whose daughter 233 Pa decays to 233 U with a strong gamma emission. Furthermore, the very rich and weakly explored chemistry of Np is also a challenge. The historical 238 Pu inventory of US-DOE has been highly consumed and supplies of available 238 Pu to support new missions have diminished. NASA and US-DOE have started an extensive project to re-establish 238 Pu production for US space missions. In Europe, ESA has also shown some interest in an European production of 238 Pu for the European space missions. In the present review, the manufacture of Np targets for 238 Pu production by irradiation, and the target processing are discussed and assessed from an European production perspective by comparing mainly US state-of-the-art with the European know-how and the current facilities. Two principal options for target fabrication stand out: aluminium-clad NpO 2 –Al CERMET and zircaloy-clad full-ceramic NpO 2 targets. The principal advantages of the well documented CERMET route can be found in the irradiation stage. These targets allow a high flexibility in heavy metal loading fraction and have high thermal performance. But, they have significant drawbacks in terms of the amount and type of nuclear waste that is generated at the back-end. Instead, the full-ceramic targets are conceptually very similar to conventional nuclear fuels, and would be preferred from back-end perspective, although a demonstration of large scale production remains yet to be done. Presently, there are no operational large scale Np target production, irradiation, processing or 238 Pu handling facilities in Europe, but the nuclear infrastructure exists and is operational to study each of the steps at least at small scale and all steps have similarities with well-established industrial capabilities in Europe.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-10-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135567894","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}
Xiaoyu Yin, Peng Wu, Yufan Zhao, Shilong Shi, Jun Liu, Feize Li, Jiali Liao, Ning Liu, Yuanyou Yang, Tu Lan
Abstract The U(VI) sorption behavior on dolomite was systematically investigated in a dilute carbonate solution using batch technique. The distribution coefficients ( K d ) increased with the increasing time and temperature, but decreased with the increase of initial U(VI) concentration and ionic strength. As the initial pH increased from 2.0 to 10.5, the K d values first increased and then decreased, mainly due to the transition from electrostatic attraction to repulsion caused by the changes in U(VI) species. The sorption process was well-described by pseudo-second-order kinetic and Freundlich isotherm models, and was spontaneous, endothermic, heterogeneous, and pH-dependent. In the presence of HA/FA, at low pH, more HAs/FAs were adsorbed on dolomite surface, providing more sorption sites for the positively charged U(VI) species, and promoting the U(VI) sorption. At high pH, more HAs/FAs were dispersed in solution, encapsulating the negatively charged U(VI) species in aggregates, and inhibiting the U(VI) sorption. The promoting and inhibiting effects of HA on the sorption process are obviously stronger than FA. XPS spectra indicated that the surface ‒OH and CO 3 2− on the hydroxylated dolomite and the –OH groups in HA/FA may be involved in U(VI) sorption. The results reported here provide valuable references for further understanding U(VI) migration in geological media.
{"title":"Sorption of U(VI) on dolomite in a dilute carbonate solution: behavior investigation and mechanism probe","authors":"Xiaoyu Yin, Peng Wu, Yufan Zhao, Shilong Shi, Jun Liu, Feize Li, Jiali Liao, Ning Liu, Yuanyou Yang, Tu Lan","doi":"10.1515/ract-2023-0216","DOIUrl":"https://doi.org/10.1515/ract-2023-0216","url":null,"abstract":"Abstract The U(VI) sorption behavior on dolomite was systematically investigated in a dilute carbonate solution using batch technique. The distribution coefficients ( K d ) increased with the increasing time and temperature, but decreased with the increase of initial U(VI) concentration and ionic strength. As the initial pH increased from 2.0 to 10.5, the K d values first increased and then decreased, mainly due to the transition from electrostatic attraction to repulsion caused by the changes in U(VI) species. The sorption process was well-described by pseudo-second-order kinetic and Freundlich isotherm models, and was spontaneous, endothermic, heterogeneous, and pH-dependent. In the presence of HA/FA, at low pH, more HAs/FAs were adsorbed on dolomite surface, providing more sorption sites for the positively charged U(VI) species, and promoting the U(VI) sorption. At high pH, more HAs/FAs were dispersed in solution, encapsulating the negatively charged U(VI) species in aggregates, and inhibiting the U(VI) sorption. The promoting and inhibiting effects of HA on the sorption process are obviously stronger than FA. XPS spectra indicated that the surface ‒OH and CO 3 2− on the hydroxylated dolomite and the –OH groups in HA/FA may be involved in U(VI) sorption. The results reported here provide valuable references for further understanding U(VI) migration in geological media.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-10-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135805252","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}
Abstract This in vitro study was conducted to evaluate the impact of gamma-irradiation on the antioxidant activity of the methanolic extracts of Crocus sativus petals. After gamma-irradiation at 5, 10, and 35 kGy doses, Folin-Ciocalteu , aluminum chloride colorimetric methods, Fourier transform infrared spectroscopy (FTIR), and high performance liquid chromatography (HPLC) techniques were deployed to analyze the irradiated and non-irradiated extracts. The obtained results were indicative of boosted levels of phenolic and total flavonoids compounds in methanolic extracts irradiated at 5 and 10 kGy. Results of the HPLC method also revealed that gamma-irradiation, especially at 5 kGy, could increase the quantity of certain polyphenols, including chlorogenic acid, epicatechin caffeic acid, and thioxanthene, in the saffron extract. In contrast, gamma-irradiation at 35 kGy exerted certain adverse effects on polyphenols contents. In conclusion, gamma-irradiation, especially at 5 kGy, could enhance the antioxidant potential of the methanolic extract of saffron petals.
{"title":"Use of gamma radiation for the antioxidant improvement of saffron [<i>Crocus sativus</i>] petal extract","authors":"Marzieh Heidarieh, Mahnoosh Parsaeimehr, Najmeh Sheikhzadeh","doi":"10.1515/ract-2023-0188","DOIUrl":"https://doi.org/10.1515/ract-2023-0188","url":null,"abstract":"Abstract This in vitro study was conducted to evaluate the impact of gamma-irradiation on the antioxidant activity of the methanolic extracts of Crocus sativus petals. After gamma-irradiation at 5, 10, and 35 kGy doses, Folin-Ciocalteu , aluminum chloride colorimetric methods, Fourier transform infrared spectroscopy (FTIR), and high performance liquid chromatography (HPLC) techniques were deployed to analyze the irradiated and non-irradiated extracts. The obtained results were indicative of boosted levels of phenolic and total flavonoids compounds in methanolic extracts irradiated at 5 and 10 kGy. Results of the HPLC method also revealed that gamma-irradiation, especially at 5 kGy, could increase the quantity of certain polyphenols, including chlorogenic acid, epicatechin caffeic acid, and thioxanthene, in the saffron extract. In contrast, gamma-irradiation at 35 kGy exerted certain adverse effects on polyphenols contents. In conclusion, gamma-irradiation, especially at 5 kGy, could enhance the antioxidant potential of the methanolic extract of saffron petals.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-10-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135805078","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}
Luis Iglesias, Jakub Kokinda, Daniel Serrano-Purroy, Albert Martínez-Torrents, Ignasi Casas, Joan de Pablo, Frederic Clarens, Javier Giménez
Abstract The release of radionuclides from high-burnup spent nuclear fuel (SNF) segments was studied at pH = 13.2 as well as the effect of the presence of calcium and silicon. The aim was to ascertain the dissolution of SNF in solutions corresponding to a high-level nuclear waste repository including concrete in different structural parts. The release of uranium at pH = 13.2 was higher than at pH = 8.4 in bicarbonate medium, while the presence of calcium resulted in a decrease of the uranium concentrations in solutions, assumed to be the consequence of the formation of a secondary solid phase such as Ca 2 U 2 O 7 . Caesium release was found higher at pH = 13.2 as well, but it was not influenced by the presence of Ca and Si at long term. On the other hand, actinide elements (plutonium, neptunium and americium) dissolution decreased at pH = 13.2, probably because of the formation of secondary solid phases. On the contrary, ruthenium and technetium release at pH = 13.2 was found to be much higher than the measured at lower pH, perhaps due to the higher dissolution kinetics of the metallic inclusions at such pH.
{"title":"Dissolution of high burn-up spent nuclear fuel at high-pH","authors":"Luis Iglesias, Jakub Kokinda, Daniel Serrano-Purroy, Albert Martínez-Torrents, Ignasi Casas, Joan de Pablo, Frederic Clarens, Javier Giménez","doi":"10.1515/ract-2023-0178","DOIUrl":"https://doi.org/10.1515/ract-2023-0178","url":null,"abstract":"Abstract The release of radionuclides from high-burnup spent nuclear fuel (SNF) segments was studied at pH = 13.2 as well as the effect of the presence of calcium and silicon. The aim was to ascertain the dissolution of SNF in solutions corresponding to a high-level nuclear waste repository including concrete in different structural parts. The release of uranium at pH = 13.2 was higher than at pH = 8.4 in bicarbonate medium, while the presence of calcium resulted in a decrease of the uranium concentrations in solutions, assumed to be the consequence of the formation of a secondary solid phase such as Ca 2 U 2 O 7 . Caesium release was found higher at pH = 13.2 as well, but it was not influenced by the presence of Ca and Si at long term. On the other hand, actinide elements (plutonium, neptunium and americium) dissolution decreased at pH = 13.2, probably because of the formation of secondary solid phases. On the contrary, ruthenium and technetium release at pH = 13.2 was found to be much higher than the measured at lower pH, perhaps due to the higher dissolution kinetics of the metallic inclusions at such pH.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-10-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135095756","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}
Abstract The stability constants of the Calcium ionophore I (i.e., N , N ´ – di[(11′- ethoxycarbonyl) undecyl] – N , N ′,4,5 -tetramethyl – 3,6 – dioxaoctane diamide) complexes with M n+ (M n+ = Li + , H 3 O + , Na + , NH 4 + , Ag + , K + , Rb + , Tl + , Cs + , Ca 2+ , Sr 2+ , Ba 2+ . Pb 2+ , Cu 2+ , Zn 2+ ) in nitrobenzene saturated with water were determined by the extraction method. These constants were found to increase in the series of Cs + < Rb + < K + < NH 4 + < Na + < Tl + < H 3 O + < Ag + < Li + and Ba 2+ < Zn 2+ < Sr 2+ < Pb 2+ < Cu 2+ < Ca 2+ .
稳定constants》抽象钙ionophore一世(神盾局,N, N´——在[(11′- ethoxycarbonyl undecyl]——N、N′4.5 -tetramethyl——360 dioxaoctane diamide complexes)和李+ M + N (N = 3, H O +、Na + 4, NH, Ag +, K, Rb, Tl + Cs + Ba + Ca 2 +, Sr, 2 +。Pb 2+， Cu 2+， Zn 2+)这些康斯坦斯发现在Cs + <中增加Rb +
{"title":"Extraction of some univalent and divalent cations into nitrobenzene in the presence of calcium ionophore I","authors":"Petr Vaňura, Emanuel Makrlík","doi":"10.1515/ract-2023-0128","DOIUrl":"https://doi.org/10.1515/ract-2023-0128","url":null,"abstract":"Abstract The stability constants of the Calcium ionophore I (i.e., N , N ´ – di[(11′- ethoxycarbonyl) undecyl] – N , N ′,4,5 -tetramethyl – 3,6 – dioxaoctane diamide) complexes with M n+ (M n+ = Li + , H 3 O + , Na + , NH 4 + , Ag + , K + , Rb + , Tl + , Cs + , Ca 2+ , Sr 2+ , Ba 2+ . Pb 2+ , Cu 2+ , Zn 2+ ) in nitrobenzene saturated with water were determined by the extraction method. These constants were found to increase in the series of Cs + < Rb + < K + < NH 4 + < Na + < Tl + < H 3 O + < Ag + < Li + and Ba 2+ < Zn 2+ < Sr 2+ < Pb 2+ < Cu 2+ < Ca 2+ .","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-10-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"134975552","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}
Carl-Christian Meyer, Ernst Artes, Markus Bender, Joachim Brötz, Christoph E. Düllmann, Constantin Haese, Egon Jäger, Birgit Kindler, Bettina Lommel, Marton Major, Maximilian Rapps, Dennis Renisch, Christina Trautmann, Alexander Yakushev
Abstract One limiting factor in progress in the discovery and study of new superheavy elements (SHE) is the maximum achievable thickness and irradiation stability of current generation actinide targets. The desired thickness of targets, using full excitation function widths, cannot be achieved with current target technology, especially the widely used molecular plating (MP). The aim of this study was to transfer progress in the electrochemistry of lanthanides and actinides to the production of targets. Here, we report on the production of lanthanide targets using anhydrous electrochemical routes. In a first irradiation series, thulium thin films with areal densities up to 1800 μg/cm 2 were produced using anhydrous triflate compounds and subjected to irradiation tests, using 6.0 MeV/u 48 Ca ions at a fluence of 3.9 × 10 14 ions/cm 2 and 8.6 MeV/u 197 Au ions at fluences in the range of 3.0 × 10 11 to 1.0 × 10 13 ions/cm 2 . The thin films were characterised before and after the irradiations using scanning electron microscopy (SEM) and energy dispersive X-ray spectroscopy (EDX).
{"title":"Fabrication, swift heavy ion irradiation, and damage analysis of lanthanide targets","authors":"Carl-Christian Meyer, Ernst Artes, Markus Bender, Joachim Brötz, Christoph E. Düllmann, Constantin Haese, Egon Jäger, Birgit Kindler, Bettina Lommel, Marton Major, Maximilian Rapps, Dennis Renisch, Christina Trautmann, Alexander Yakushev","doi":"10.1515/ract-2023-0197","DOIUrl":"https://doi.org/10.1515/ract-2023-0197","url":null,"abstract":"Abstract One limiting factor in progress in the discovery and study of new superheavy elements (SHE) is the maximum achievable thickness and irradiation stability of current generation actinide targets. The desired thickness of targets, using full excitation function widths, cannot be achieved with current target technology, especially the widely used molecular plating (MP). The aim of this study was to transfer progress in the electrochemistry of lanthanides and actinides to the production of targets. Here, we report on the production of lanthanide targets using anhydrous electrochemical routes. In a first irradiation series, thulium thin films with areal densities up to 1800 μg/cm 2 were produced using anhydrous triflate compounds and subjected to irradiation tests, using 6.0 MeV/u 48 Ca ions at a fluence of 3.9 × 10 14 ions/cm 2 and 8.6 MeV/u 197 Au ions at fluences in the range of 3.0 × 10 11 to 1.0 × 10 13 ions/cm 2 . The thin films were characterised before and after the irradiations using scanning electron microscopy (SEM) and energy dispersive X-ray spectroscopy (EDX).","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-10-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135689363","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}
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