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":"69 9","pages":"0"},"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":"27 1","pages":"0"},"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":"45 1","pages":"0"},"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":"4 1","pages":"0"},"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":"10 1","pages":"0"},"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":"47 1","pages":"0"},"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}
Haladhara Naik, Ram Janam Singh, Srikant Pandurang Dange, Wooyoung Jang
Abstract Independent isomeric yield ratios (IR) of 130,132 Sb, 131,133 Te, 134,136 I, 135 Xe and 138 Cs have been measured in the epi-cadmium neutron induced fission of 241 Pu by using an off-line gamma-ray spectrometric technique. The average neutron energy (< E n >) of the epi-cadmium reactor neutron spectrum is 1.9 MeV. From the IR values, root mean square fragment angular momenta ( J RMS ) were deduced by using spin dependent statistical model analysis. Effect of nuclear structure on J RMS values was examined. The present data in the epi-cadmium neutron induced fission of 241 Pu were compared with the similar data in the thermal neutron induced fission of 241 Pu to examine the role of excitation energy on fragment angular momentum.
摘要:利用离线伽玛射线谱技术，测定了241 Pu在镉镉中子诱导裂变过程中130,132 Sb, 131,133 Te, 134,136 I, 135 Xe和138 Cs的独立同分异构体产率(IR)。中子平均能量(<epi-镉反应堆中子谱的E n >)为1.9 MeV。利用自旋相关统计模型分析，从红外光谱值推导出碎片角动量的均方根。研究了核结构对jrms值的影响。本文将外镉中子诱导241钚裂变的实验数据与热中子诱导241钚裂变的实验数据进行了比较，探讨了激发能对碎片角动量的影响。
{"title":"Independent isomeric yield ratios of fission products in the epi-cadmium neutron induced fission of <sup>241</sup>Pu","authors":"Haladhara Naik, Ram Janam Singh, Srikant Pandurang Dange, Wooyoung Jang","doi":"10.1515/ract-2023-0177","DOIUrl":"https://doi.org/10.1515/ract-2023-0177","url":null,"abstract":"Abstract Independent isomeric yield ratios (IR) of 130,132 Sb, 131,133 Te, 134,136 I, 135 Xe and 138 Cs have been measured in the epi-cadmium neutron induced fission of 241 Pu by using an off-line gamma-ray spectrometric technique. The average neutron energy (< E n >) of the epi-cadmium reactor neutron spectrum is 1.9 MeV. From the IR values, root mean square fragment angular momenta ( J RMS ) were deduced by using spin dependent statistical model analysis. Effect of nuclear structure on J RMS values was examined. The present data in the epi-cadmium neutron induced fission of 241 Pu were compared with the similar data in the thermal neutron induced fission of 241 Pu to examine the role of excitation energy on fragment angular momentum.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"26 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2023-09-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135816898","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}
Nabila Taïbouni, Arezki Amokrane, Tarek Azli, Ben Amor Mohammed Larbi, Naima Belouadah, Khelifa Boukeffoussa, Camelia Yasmine Medour, Hamza Zouad, Mohammed Messaoudi
Abstract The energy-dispersive X-ray fluorescence (ED-XRF) technique has been used for measurements of K α , K β , and total K X-rays emission cross sections induced by photons, as well as K-shell fluorescence yields for pure elements with 22 ⩽ Z ⩽ 49. These metals have been irradiated at 59.54 KeV excitation energy from an 241 Am annular radioactive source. The characteristic K X-rays emitted by the targets have been detected with a Silicon drift detector (SDD); the net areas of the K α and K β spectral peaks have been determined using the fitting process of PYMCA software. The obtained experimental values of the K X-ray fluorescence cross sections and the K-shell fluorescence yields were compared to the theoretical calculated ones and also to the experimental results obtained from a different experimental setup using a point source. The obtained values were between (6.84 ± 0.55 b/at.) and (891.0 ± 67.5 b/at.) for pure metals form Scandium to Indium. Experimental values were in good agreement with theoretical values within limits of uncertainty, as well as with the data reported in the literature. Moreover, the experimental determination of K X-ray fluorescence cross-section of scandium (Sc) at 59.54 KeV has not been preceded as far as we know. The value obtained is (6.84 ± 0.55 b/at). This new result obtained maybe contribute to the enrichment of the available databases.
{"title":"Experimental measurements of X-rays emission cross sections induced by photons","authors":"Nabila Taïbouni, Arezki Amokrane, Tarek Azli, Ben Amor Mohammed Larbi, Naima Belouadah, Khelifa Boukeffoussa, Camelia Yasmine Medour, Hamza Zouad, Mohammed Messaoudi","doi":"10.1515/ract-2023-0179","DOIUrl":"https://doi.org/10.1515/ract-2023-0179","url":null,"abstract":"Abstract The energy-dispersive X-ray fluorescence (ED-XRF) technique has been used for measurements of K α , K β , and total K X-rays emission cross sections induced by photons, as well as K-shell fluorescence yields for pure elements with 22 ⩽ Z ⩽ 49. These metals have been irradiated at 59.54 KeV excitation energy from an 241 Am annular radioactive source. The characteristic K X-rays emitted by the targets have been detected with a Silicon drift detector (SDD); the net areas of the K α and K β spectral peaks have been determined using the fitting process of PYMCA software. The obtained experimental values of the K X-ray fluorescence cross sections and the K-shell fluorescence yields were compared to the theoretical calculated ones and also to the experimental results obtained from a different experimental setup using a point source. The obtained values were between (6.84 ± 0.55 b/at.) and (891.0 ± 67.5 b/at.) for pure metals form Scandium to Indium. Experimental values were in good agreement with theoretical values within limits of uncertainty, as well as with the data reported in the literature. Moreover, the experimental determination of K X-ray fluorescence cross-section of scandium (Sc) at 59.54 KeV has not been preceded as far as we know. The value obtained is (6.84 ± 0.55 b/at). This new result obtained maybe contribute to the enrichment of the available databases.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"23 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2023-09-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"136155234","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 Selective removal of 99 TcO 4 − from complex radioactive wastewater is a challenging but meaningful task since it is important for both spent fuel reprocessing and 99 TcO 4 − leakage handling. Here, we synthesized a series of functionalized PAF-1 framework materials, PAF-1-C-N2, PAF-1-N2-C4, PAF-1-IM and PAF-1-PY, by grafting quaternary ammonium, imidazolium and pyridinium onto the PAF framework as active sites, respectively, which purpose is to screen functional groups with high affinity for TcO 4 − . The structures and morphological characteristics of the four adsorbents were characterized by N 2 adsorption-desorption, Fourier transform infrared spectroscopy (FT-IR), and scanning electron microscope (SEM). These materials exhibit high selectivity for TcO 4 − /ReO 4 − , rapid adsorption kinetics (reaching equilibrium within 30 s), and a wide pH range (pH 3–11) for ReO 4 − /TcO 4 − adsorption. Among them, PAF-1-IM had the best adsorption performance, and the partition coefficient K d reached 1.27 × 10 6 mL/g. 97.1 % and 96.9 % of ReO 4 − could be removed by PAF-1-IM even when the concentrations of PO 4 3− and SO 4 2− are 1000 times the concentration of ReO 4 − , respectively. When the solid-liquid ratio is 10 g/L, 93.7 % of TcO 4 − can be removed from the simulated Low Active Wastewater (LAW), which is higher than most other TcO 4 − adsorbents. X-ray energy dispersive spectroscopy (EDS) and FT-IR suggest the adsorption process was anion exchange.
{"title":"Highly efficient uptake of TcO<sub>4</sub> <sup>−</sup>/ReO<sub>4</sub> <sup>−</sup> by functionalized PAFs","authors":"Xupeng Zhi, Xinlong Chen, Yinglin Shen, Xiaomin Li, Suliang Yang, Shengdong Zhang","doi":"10.1515/ract-2023-0218","DOIUrl":"https://doi.org/10.1515/ract-2023-0218","url":null,"abstract":"Abstract Selective removal of 99 TcO 4 − from complex radioactive wastewater is a challenging but meaningful task since it is important for both spent fuel reprocessing and 99 TcO 4 − leakage handling. Here, we synthesized a series of functionalized PAF-1 framework materials, PAF-1-C-N2, PAF-1-N2-C4, PAF-1-IM and PAF-1-PY, by grafting quaternary ammonium, imidazolium and pyridinium onto the PAF framework as active sites, respectively, which purpose is to screen functional groups with high affinity for TcO 4 − . The structures and morphological characteristics of the four adsorbents were characterized by N 2 adsorption-desorption, Fourier transform infrared spectroscopy (FT-IR), and scanning electron microscope (SEM). These materials exhibit high selectivity for TcO 4 − /ReO 4 − , rapid adsorption kinetics (reaching equilibrium within 30 s), and a wide pH range (pH 3–11) for ReO 4 − /TcO 4 − adsorption. Among them, PAF-1-IM had the best adsorption performance, and the partition coefficient K d reached 1.27 × 10 6 mL/g. 97.1 % and 96.9 % of ReO 4 − could be removed by PAF-1-IM even when the concentrations of PO 4 3− and SO 4 2− are 1000 times the concentration of ReO 4 − , respectively. When the solid-liquid ratio is 10 g/L, 93.7 % of TcO 4 − can be removed from the simulated Low Active Wastewater (LAW), which is higher than most other TcO 4 − adsorbents. X-ray energy dispersive spectroscopy (EDS) and FT-IR suggest the adsorption process was anion exchange.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"80 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2023-09-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"136263886","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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