Oxygen isotopes of fuel pellets from the fifth collaborative materials exercise and uranium oxides reference materials determined by continuous flow laser fluorination mass spectrometry for nuclear forensic applications
Abstract Uranium oxides are essential materials in the production process of nuclear fuel for civilian or military applications. As such, identifying their geological origin, manufacturing process and age, plays a central role in the field of nuclear forensic. This study aims to expand the tradition...
Ausführliche Beschreibung
Autor*in: |
Assulin, Maor [verfasserIn] Yam, Ruth [verfasserIn] Brandis, Michal [verfasserIn] Rubinshtein, Arnon [verfasserIn] Sasson-Zukran, Revital [verfasserIn] Elish, Eyal [verfasserIn] Shemesh, Aldo [verfasserIn] |
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Format: |
E-Artikel |
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Sprache: |
Englisch |
Erschienen: |
2021 |
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Schlagwörter: |
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Anmerkung: |
© Akadémiai Kiadó, Budapest, Hungary 2021 |
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Übergeordnetes Werk: |
Enthalten in: Journal of radioanalytical and nuclear chemistry - Dordrecht [u.a.] : Springer Science + Business Media B.V., 1968, 329(2021), 2 vom: 04. Juli, Seite 757-768 |
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Übergeordnetes Werk: |
volume:329 ; year:2021 ; number:2 ; day:04 ; month:07 ; pages:757-768 |
Links: |
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DOI / URN: |
10.1007/s10967-021-07858-x |
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Katalog-ID: |
SPR044695039 |
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520 | |a Abstract Uranium oxides are essential materials in the production process of nuclear fuel for civilian or military applications. As such, identifying their geological origin, manufacturing process and age, plays a central role in the field of nuclear forensic. This study aims to expand the traditional characterization analytical techniques by measuring the oxygen isotopic composition of various uranium oxides (e.g., $ UO_{2} $, $ U_{3} %$ O_{8} $), uranium ore concentrates (UOC). We apply it to $ UO_{2} $ pellets from the Fifth Collaborative Materials Exercise (CMX-5). We developed an accurate laser fluorination in line with continuous-flow mass spectrometry analytical method for measuring oxygen isotopes in sub-milligram nuclear materials, including raw materials and selected materials from several stages of the fuel production cycle. We report for the first time, on the oxygen isotope composition of the two $ UO_{2} $ fuel pellets, used for the international CMX-5. We show that $ δ^{18} $O of these pellets differ by 1.7‰, which probably originates from their manufacturing processes. CUP-2, a UOC, was used to demonstrate the challenge of measuring isotope composition of hydrated forms of uranium oxides. $ U_{3} %$ O_{8} $ was found to exhibit lower than expected, by stoichiometric formula, oxygen contents. That might originate from oxygen loss during the pre-fluorination process, or indicates the presence of more than one phase within this particular $ U_{3} %$ O_{8} $ system. | ||
650 | 4 | |a Uranium oxides |7 (dpeaa)DE-He213 | |
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650 | 4 | |a Oxygen isotopes |7 (dpeaa)DE-He213 | |
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650 | 4 | |a Nuclear forensics |7 (dpeaa)DE-He213 | |
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700 | 1 | |a Elish, Eyal |e verfasserin |4 aut | |
700 | 1 | |a Shemesh, Aldo |e verfasserin |4 aut | |
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10.1007/s10967-021-07858-x doi (DE-627)SPR044695039 (SPR)s10967-021-07858-x-e DE-627 ger DE-627 rakwb eng 540 ASE 35.00 bkl Assulin, Maor verfasserin aut Oxygen isotopes of fuel pellets from the fifth collaborative materials exercise and uranium oxides reference materials determined by continuous flow laser fluorination mass spectrometry for nuclear forensic applications 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier © Akadémiai Kiadó, Budapest, Hungary 2021 Abstract Uranium oxides are essential materials in the production process of nuclear fuel for civilian or military applications. As such, identifying their geological origin, manufacturing process and age, plays a central role in the field of nuclear forensic. This study aims to expand the traditional characterization analytical techniques by measuring the oxygen isotopic composition of various uranium oxides (e.g., $ UO_{2} $, $ U_{3} %$ O_{8} $), uranium ore concentrates (UOC). We apply it to $ UO_{2} $ pellets from the Fifth Collaborative Materials Exercise (CMX-5). We developed an accurate laser fluorination in line with continuous-flow mass spectrometry analytical method for measuring oxygen isotopes in sub-milligram nuclear materials, including raw materials and selected materials from several stages of the fuel production cycle. We report for the first time, on the oxygen isotope composition of the two $ UO_{2} $ fuel pellets, used for the international CMX-5. We show that $ δ^{18} $O of these pellets differ by 1.7‰, which probably originates from their manufacturing processes. CUP-2, a UOC, was used to demonstrate the challenge of measuring isotope composition of hydrated forms of uranium oxides. $ U_{3} %$ O_{8} $ was found to exhibit lower than expected, by stoichiometric formula, oxygen contents. That might originate from oxygen loss during the pre-fluorination process, or indicates the presence of more than one phase within this particular $ U_{3} %$ O_{8} $ system. Uranium oxides (dpeaa)DE-He213 CMX-5 (dpeaa)DE-He213 Nuclear fuel pellet (dpeaa)DE-He213 Oxygen isotopes (dpeaa)DE-He213 Uranium ore concentrate (dpeaa)DE-He213 Nuclear forensics (dpeaa)DE-He213 Yam, Ruth verfasserin aut Brandis, Michal verfasserin aut Rubinshtein, Arnon verfasserin aut Sasson-Zukran, Revital verfasserin aut Elish, Eyal verfasserin aut Shemesh, Aldo verfasserin aut Enthalten in Journal of radioanalytical and nuclear chemistry Dordrecht [u.a.] : Springer Science + Business Media B.V., 1968 329(2021), 2 vom: 04. Juli, Seite 757-768 (DE-627)320578011 (DE-600)2017242-4 1588-2780 nnns volume:329 year:2021 number:2 day:04 month:07 pages:757-768 https://dx.doi.org/10.1007/s10967-021-07858-x lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_SPRINGER SSG-OLC-PHA GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_120 GBV_ILN_138 GBV_ILN_150 GBV_ILN_151 GBV_ILN_152 GBV_ILN_161 GBV_ILN_170 GBV_ILN_171 GBV_ILN_187 GBV_ILN_206 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_250 GBV_ILN_281 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_636 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2031 GBV_ILN_2034 GBV_ILN_2037 GBV_ILN_2038 GBV_ILN_2039 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2057 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2088 GBV_ILN_2093 GBV_ILN_2106 GBV_ILN_2107 GBV_ILN_2108 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2119 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2144 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2188 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2446 GBV_ILN_2470 GBV_ILN_2472 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_2548 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4246 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4328 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4336 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 35.00 ASE AR 329 2021 2 04 07 757-768 |
spelling |
10.1007/s10967-021-07858-x doi (DE-627)SPR044695039 (SPR)s10967-021-07858-x-e DE-627 ger DE-627 rakwb eng 540 ASE 35.00 bkl Assulin, Maor verfasserin aut Oxygen isotopes of fuel pellets from the fifth collaborative materials exercise and uranium oxides reference materials determined by continuous flow laser fluorination mass spectrometry for nuclear forensic applications 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier © Akadémiai Kiadó, Budapest, Hungary 2021 Abstract Uranium oxides are essential materials in the production process of nuclear fuel for civilian or military applications. As such, identifying their geological origin, manufacturing process and age, plays a central role in the field of nuclear forensic. This study aims to expand the traditional characterization analytical techniques by measuring the oxygen isotopic composition of various uranium oxides (e.g., $ UO_{2} $, $ U_{3} %$ O_{8} $), uranium ore concentrates (UOC). We apply it to $ UO_{2} $ pellets from the Fifth Collaborative Materials Exercise (CMX-5). We developed an accurate laser fluorination in line with continuous-flow mass spectrometry analytical method for measuring oxygen isotopes in sub-milligram nuclear materials, including raw materials and selected materials from several stages of the fuel production cycle. We report for the first time, on the oxygen isotope composition of the two $ UO_{2} $ fuel pellets, used for the international CMX-5. We show that $ δ^{18} $O of these pellets differ by 1.7‰, which probably originates from their manufacturing processes. CUP-2, a UOC, was used to demonstrate the challenge of measuring isotope composition of hydrated forms of uranium oxides. $ U_{3} %$ O_{8} $ was found to exhibit lower than expected, by stoichiometric formula, oxygen contents. That might originate from oxygen loss during the pre-fluorination process, or indicates the presence of more than one phase within this particular $ U_{3} %$ O_{8} $ system. Uranium oxides (dpeaa)DE-He213 CMX-5 (dpeaa)DE-He213 Nuclear fuel pellet (dpeaa)DE-He213 Oxygen isotopes (dpeaa)DE-He213 Uranium ore concentrate (dpeaa)DE-He213 Nuclear forensics (dpeaa)DE-He213 Yam, Ruth verfasserin aut Brandis, Michal verfasserin aut Rubinshtein, Arnon verfasserin aut Sasson-Zukran, Revital verfasserin aut Elish, Eyal verfasserin aut Shemesh, Aldo verfasserin aut Enthalten in Journal of radioanalytical and nuclear chemistry Dordrecht [u.a.] : Springer Science + Business Media B.V., 1968 329(2021), 2 vom: 04. Juli, Seite 757-768 (DE-627)320578011 (DE-600)2017242-4 1588-2780 nnns volume:329 year:2021 number:2 day:04 month:07 pages:757-768 https://dx.doi.org/10.1007/s10967-021-07858-x lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_SPRINGER SSG-OLC-PHA GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_120 GBV_ILN_138 GBV_ILN_150 GBV_ILN_151 GBV_ILN_152 GBV_ILN_161 GBV_ILN_170 GBV_ILN_171 GBV_ILN_187 GBV_ILN_206 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_250 GBV_ILN_281 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_636 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2031 GBV_ILN_2034 GBV_ILN_2037 GBV_ILN_2038 GBV_ILN_2039 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2057 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2088 GBV_ILN_2093 GBV_ILN_2106 GBV_ILN_2107 GBV_ILN_2108 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2119 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2144 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2188 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2446 GBV_ILN_2470 GBV_ILN_2472 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_2548 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4246 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4328 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4336 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 35.00 ASE AR 329 2021 2 04 07 757-768 |
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10.1007/s10967-021-07858-x doi (DE-627)SPR044695039 (SPR)s10967-021-07858-x-e DE-627 ger DE-627 rakwb eng 540 ASE 35.00 bkl Assulin, Maor verfasserin aut Oxygen isotopes of fuel pellets from the fifth collaborative materials exercise and uranium oxides reference materials determined by continuous flow laser fluorination mass spectrometry for nuclear forensic applications 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier © Akadémiai Kiadó, Budapest, Hungary 2021 Abstract Uranium oxides are essential materials in the production process of nuclear fuel for civilian or military applications. As such, identifying their geological origin, manufacturing process and age, plays a central role in the field of nuclear forensic. This study aims to expand the traditional characterization analytical techniques by measuring the oxygen isotopic composition of various uranium oxides (e.g., $ UO_{2} $, $ U_{3} %$ O_{8} $), uranium ore concentrates (UOC). We apply it to $ UO_{2} $ pellets from the Fifth Collaborative Materials Exercise (CMX-5). We developed an accurate laser fluorination in line with continuous-flow mass spectrometry analytical method for measuring oxygen isotopes in sub-milligram nuclear materials, including raw materials and selected materials from several stages of the fuel production cycle. We report for the first time, on the oxygen isotope composition of the two $ UO_{2} $ fuel pellets, used for the international CMX-5. We show that $ δ^{18} $O of these pellets differ by 1.7‰, which probably originates from their manufacturing processes. CUP-2, a UOC, was used to demonstrate the challenge of measuring isotope composition of hydrated forms of uranium oxides. $ U_{3} %$ O_{8} $ was found to exhibit lower than expected, by stoichiometric formula, oxygen contents. That might originate from oxygen loss during the pre-fluorination process, or indicates the presence of more than one phase within this particular $ U_{3} %$ O_{8} $ system. Uranium oxides (dpeaa)DE-He213 CMX-5 (dpeaa)DE-He213 Nuclear fuel pellet (dpeaa)DE-He213 Oxygen isotopes (dpeaa)DE-He213 Uranium ore concentrate (dpeaa)DE-He213 Nuclear forensics (dpeaa)DE-He213 Yam, Ruth verfasserin aut Brandis, Michal verfasserin aut Rubinshtein, Arnon verfasserin aut Sasson-Zukran, Revital verfasserin aut Elish, Eyal verfasserin aut Shemesh, Aldo verfasserin aut Enthalten in Journal of radioanalytical and nuclear chemistry Dordrecht [u.a.] : Springer Science + Business Media B.V., 1968 329(2021), 2 vom: 04. Juli, Seite 757-768 (DE-627)320578011 (DE-600)2017242-4 1588-2780 nnns volume:329 year:2021 number:2 day:04 month:07 pages:757-768 https://dx.doi.org/10.1007/s10967-021-07858-x lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_SPRINGER SSG-OLC-PHA GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_120 GBV_ILN_138 GBV_ILN_150 GBV_ILN_151 GBV_ILN_152 GBV_ILN_161 GBV_ILN_170 GBV_ILN_171 GBV_ILN_187 GBV_ILN_206 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_250 GBV_ILN_281 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_636 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2031 GBV_ILN_2034 GBV_ILN_2037 GBV_ILN_2038 GBV_ILN_2039 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2057 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2088 GBV_ILN_2093 GBV_ILN_2106 GBV_ILN_2107 GBV_ILN_2108 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2119 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2144 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2188 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2446 GBV_ILN_2470 GBV_ILN_2472 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_2548 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4246 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4328 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4336 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 35.00 ASE AR 329 2021 2 04 07 757-768 |
allfieldsGer |
10.1007/s10967-021-07858-x doi (DE-627)SPR044695039 (SPR)s10967-021-07858-x-e DE-627 ger DE-627 rakwb eng 540 ASE 35.00 bkl Assulin, Maor verfasserin aut Oxygen isotopes of fuel pellets from the fifth collaborative materials exercise and uranium oxides reference materials determined by continuous flow laser fluorination mass spectrometry for nuclear forensic applications 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier © Akadémiai Kiadó, Budapest, Hungary 2021 Abstract Uranium oxides are essential materials in the production process of nuclear fuel for civilian or military applications. As such, identifying their geological origin, manufacturing process and age, plays a central role in the field of nuclear forensic. This study aims to expand the traditional characterization analytical techniques by measuring the oxygen isotopic composition of various uranium oxides (e.g., $ UO_{2} $, $ U_{3} %$ O_{8} $), uranium ore concentrates (UOC). We apply it to $ UO_{2} $ pellets from the Fifth Collaborative Materials Exercise (CMX-5). We developed an accurate laser fluorination in line with continuous-flow mass spectrometry analytical method for measuring oxygen isotopes in sub-milligram nuclear materials, including raw materials and selected materials from several stages of the fuel production cycle. We report for the first time, on the oxygen isotope composition of the two $ UO_{2} $ fuel pellets, used for the international CMX-5. We show that $ δ^{18} $O of these pellets differ by 1.7‰, which probably originates from their manufacturing processes. CUP-2, a UOC, was used to demonstrate the challenge of measuring isotope composition of hydrated forms of uranium oxides. $ U_{3} %$ O_{8} $ was found to exhibit lower than expected, by stoichiometric formula, oxygen contents. That might originate from oxygen loss during the pre-fluorination process, or indicates the presence of more than one phase within this particular $ U_{3} %$ O_{8} $ system. Uranium oxides (dpeaa)DE-He213 CMX-5 (dpeaa)DE-He213 Nuclear fuel pellet (dpeaa)DE-He213 Oxygen isotopes (dpeaa)DE-He213 Uranium ore concentrate (dpeaa)DE-He213 Nuclear forensics (dpeaa)DE-He213 Yam, Ruth verfasserin aut Brandis, Michal verfasserin aut Rubinshtein, Arnon verfasserin aut Sasson-Zukran, Revital verfasserin aut Elish, Eyal verfasserin aut Shemesh, Aldo verfasserin aut Enthalten in Journal of radioanalytical and nuclear chemistry Dordrecht [u.a.] : Springer Science + Business Media B.V., 1968 329(2021), 2 vom: 04. Juli, Seite 757-768 (DE-627)320578011 (DE-600)2017242-4 1588-2780 nnns volume:329 year:2021 number:2 day:04 month:07 pages:757-768 https://dx.doi.org/10.1007/s10967-021-07858-x lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_SPRINGER SSG-OLC-PHA GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_120 GBV_ILN_138 GBV_ILN_150 GBV_ILN_151 GBV_ILN_152 GBV_ILN_161 GBV_ILN_170 GBV_ILN_171 GBV_ILN_187 GBV_ILN_206 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_250 GBV_ILN_281 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_636 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2031 GBV_ILN_2034 GBV_ILN_2037 GBV_ILN_2038 GBV_ILN_2039 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2057 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2088 GBV_ILN_2093 GBV_ILN_2106 GBV_ILN_2107 GBV_ILN_2108 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2119 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2144 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2188 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2446 GBV_ILN_2470 GBV_ILN_2472 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_2548 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4246 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4328 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4336 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 35.00 ASE AR 329 2021 2 04 07 757-768 |
allfieldsSound |
10.1007/s10967-021-07858-x doi (DE-627)SPR044695039 (SPR)s10967-021-07858-x-e DE-627 ger DE-627 rakwb eng 540 ASE 35.00 bkl Assulin, Maor verfasserin aut Oxygen isotopes of fuel pellets from the fifth collaborative materials exercise and uranium oxides reference materials determined by continuous flow laser fluorination mass spectrometry for nuclear forensic applications 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier © Akadémiai Kiadó, Budapest, Hungary 2021 Abstract Uranium oxides are essential materials in the production process of nuclear fuel for civilian or military applications. As such, identifying their geological origin, manufacturing process and age, plays a central role in the field of nuclear forensic. This study aims to expand the traditional characterization analytical techniques by measuring the oxygen isotopic composition of various uranium oxides (e.g., $ UO_{2} $, $ U_{3} %$ O_{8} $), uranium ore concentrates (UOC). We apply it to $ UO_{2} $ pellets from the Fifth Collaborative Materials Exercise (CMX-5). We developed an accurate laser fluorination in line with continuous-flow mass spectrometry analytical method for measuring oxygen isotopes in sub-milligram nuclear materials, including raw materials and selected materials from several stages of the fuel production cycle. We report for the first time, on the oxygen isotope composition of the two $ UO_{2} $ fuel pellets, used for the international CMX-5. We show that $ δ^{18} $O of these pellets differ by 1.7‰, which probably originates from their manufacturing processes. CUP-2, a UOC, was used to demonstrate the challenge of measuring isotope composition of hydrated forms of uranium oxides. $ U_{3} %$ O_{8} $ was found to exhibit lower than expected, by stoichiometric formula, oxygen contents. That might originate from oxygen loss during the pre-fluorination process, or indicates the presence of more than one phase within this particular $ U_{3} %$ O_{8} $ system. Uranium oxides (dpeaa)DE-He213 CMX-5 (dpeaa)DE-He213 Nuclear fuel pellet (dpeaa)DE-He213 Oxygen isotopes (dpeaa)DE-He213 Uranium ore concentrate (dpeaa)DE-He213 Nuclear forensics (dpeaa)DE-He213 Yam, Ruth verfasserin aut Brandis, Michal verfasserin aut Rubinshtein, Arnon verfasserin aut Sasson-Zukran, Revital verfasserin aut Elish, Eyal verfasserin aut Shemesh, Aldo verfasserin aut Enthalten in Journal of radioanalytical and nuclear chemistry Dordrecht [u.a.] : Springer Science + Business Media B.V., 1968 329(2021), 2 vom: 04. Juli, Seite 757-768 (DE-627)320578011 (DE-600)2017242-4 1588-2780 nnns volume:329 year:2021 number:2 day:04 month:07 pages:757-768 https://dx.doi.org/10.1007/s10967-021-07858-x lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_SPRINGER SSG-OLC-PHA GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_120 GBV_ILN_138 GBV_ILN_150 GBV_ILN_151 GBV_ILN_152 GBV_ILN_161 GBV_ILN_170 GBV_ILN_171 GBV_ILN_187 GBV_ILN_206 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_250 GBV_ILN_281 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_636 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2031 GBV_ILN_2034 GBV_ILN_2037 GBV_ILN_2038 GBV_ILN_2039 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2057 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2088 GBV_ILN_2093 GBV_ILN_2106 GBV_ILN_2107 GBV_ILN_2108 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2119 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2144 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2188 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2446 GBV_ILN_2470 GBV_ILN_2472 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_2548 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4246 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4328 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4336 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 35.00 ASE AR 329 2021 2 04 07 757-768 |
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Enthalten in Journal of radioanalytical and nuclear chemistry 329(2021), 2 vom: 04. Juli, Seite 757-768 volume:329 year:2021 number:2 day:04 month:07 pages:757-768 |
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Enthalten in Journal of radioanalytical and nuclear chemistry 329(2021), 2 vom: 04. Juli, Seite 757-768 volume:329 year:2021 number:2 day:04 month:07 pages:757-768 |
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Uranium oxides CMX-5 Nuclear fuel pellet Oxygen isotopes Uranium ore concentrate Nuclear forensics |
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Assulin, Maor @@aut@@ Yam, Ruth @@aut@@ Brandis, Michal @@aut@@ Rubinshtein, Arnon @@aut@@ Sasson-Zukran, Revital @@aut@@ Elish, Eyal @@aut@@ Shemesh, Aldo @@aut@@ |
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2021-07-04T00:00:00Z |
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<?xml version="1.0" encoding="UTF-8"?><collection xmlns="http://www.loc.gov/MARC21/slim"><record><leader>01000caa a22002652 4500</leader><controlfield tag="001">SPR044695039</controlfield><controlfield tag="003">DE-627</controlfield><controlfield tag="005">20230519231556.0</controlfield><controlfield tag="007">cr uuu---uuuuu</controlfield><controlfield tag="008">210730s2021 xx |||||o 00| ||eng c</controlfield><datafield tag="024" ind1="7" ind2=" "><subfield code="a">10.1007/s10967-021-07858-x</subfield><subfield code="2">doi</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(DE-627)SPR044695039</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(SPR)s10967-021-07858-x-e</subfield></datafield><datafield tag="040" ind1=" " ind2=" "><subfield code="a">DE-627</subfield><subfield code="b">ger</subfield><subfield code="c">DE-627</subfield><subfield code="e">rakwb</subfield></datafield><datafield tag="041" ind1=" " ind2=" "><subfield code="a">eng</subfield></datafield><datafield tag="082" ind1="0" ind2="4"><subfield code="a">540</subfield><subfield code="q">ASE</subfield></datafield><datafield tag="084" ind1=" " ind2=" "><subfield code="a">35.00</subfield><subfield code="2">bkl</subfield></datafield><datafield tag="100" ind1="1" ind2=" "><subfield code="a">Assulin, Maor</subfield><subfield code="e">verfasserin</subfield><subfield code="4">aut</subfield></datafield><datafield tag="245" ind1="1" ind2="0"><subfield code="a">Oxygen isotopes of fuel pellets from the fifth collaborative materials exercise and uranium oxides reference materials determined by continuous flow laser fluorination mass spectrometry for nuclear forensic applications</subfield></datafield><datafield tag="264" ind1=" " ind2="1"><subfield code="c">2021</subfield></datafield><datafield tag="336" ind1=" " ind2=" "><subfield code="a">Text</subfield><subfield code="b">txt</subfield><subfield code="2">rdacontent</subfield></datafield><datafield tag="337" ind1=" " ind2=" "><subfield code="a">Computermedien</subfield><subfield code="b">c</subfield><subfield code="2">rdamedia</subfield></datafield><datafield tag="338" ind1=" " ind2=" "><subfield code="a">Online-Ressource</subfield><subfield code="b">cr</subfield><subfield code="2">rdacarrier</subfield></datafield><datafield tag="500" ind1=" " ind2=" "><subfield code="a">© Akadémiai Kiadó, Budapest, Hungary 2021</subfield></datafield><datafield tag="520" ind1=" " ind2=" "><subfield code="a">Abstract Uranium oxides are essential materials in the production process of nuclear fuel for civilian or military applications. As such, identifying their geological origin, manufacturing process and age, plays a central role in the field of nuclear forensic. This study aims to expand the traditional characterization analytical techniques by measuring the oxygen isotopic composition of various uranium oxides (e.g., $ UO_{2} $, $ U_{3} %$ O_{8} $), uranium ore concentrates (UOC). We apply it to $ UO_{2} $ pellets from the Fifth Collaborative Materials Exercise (CMX-5). We developed an accurate laser fluorination in line with continuous-flow mass spectrometry analytical method for measuring oxygen isotopes in sub-milligram nuclear materials, including raw materials and selected materials from several stages of the fuel production cycle. We report for the first time, on the oxygen isotope composition of the two $ UO_{2} $ fuel pellets, used for the international CMX-5. We show that $ δ^{18} $O of these pellets differ by 1.7‰, which probably originates from their manufacturing processes. CUP-2, a UOC, was used to demonstrate the challenge of measuring isotope composition of hydrated forms of uranium oxides. $ U_{3} %$ O_{8} $ was found to exhibit lower than expected, by stoichiometric formula, oxygen contents. 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Assulin, Maor |
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Assulin, Maor ddc 540 bkl 35.00 misc Uranium oxides misc CMX-5 misc Nuclear fuel pellet misc Oxygen isotopes misc Uranium ore concentrate misc Nuclear forensics Oxygen isotopes of fuel pellets from the fifth collaborative materials exercise and uranium oxides reference materials determined by continuous flow laser fluorination mass spectrometry for nuclear forensic applications |
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540 ASE 35.00 bkl Oxygen isotopes of fuel pellets from the fifth collaborative materials exercise and uranium oxides reference materials determined by continuous flow laser fluorination mass spectrometry for nuclear forensic applications Uranium oxides (dpeaa)DE-He213 CMX-5 (dpeaa)DE-He213 Nuclear fuel pellet (dpeaa)DE-He213 Oxygen isotopes (dpeaa)DE-He213 Uranium ore concentrate (dpeaa)DE-He213 Nuclear forensics (dpeaa)DE-He213 |
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ddc 540 bkl 35.00 misc Uranium oxides misc CMX-5 misc Nuclear fuel pellet misc Oxygen isotopes misc Uranium ore concentrate misc Nuclear forensics |
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Oxygen isotopes of fuel pellets from the fifth collaborative materials exercise and uranium oxides reference materials determined by continuous flow laser fluorination mass spectrometry for nuclear forensic applications |
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Oxygen isotopes of fuel pellets from the fifth collaborative materials exercise and uranium oxides reference materials determined by continuous flow laser fluorination mass spectrometry for nuclear forensic applications |
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Assulin, Maor |
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Assulin, Maor Yam, Ruth Brandis, Michal Rubinshtein, Arnon Sasson-Zukran, Revital Elish, Eyal Shemesh, Aldo |
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oxygen isotopes of fuel pellets from the fifth collaborative materials exercise and uranium oxides reference materials determined by continuous flow laser fluorination mass spectrometry for nuclear forensic applications |
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Oxygen isotopes of fuel pellets from the fifth collaborative materials exercise and uranium oxides reference materials determined by continuous flow laser fluorination mass spectrometry for nuclear forensic applications |
abstract |
Abstract Uranium oxides are essential materials in the production process of nuclear fuel for civilian or military applications. As such, identifying their geological origin, manufacturing process and age, plays a central role in the field of nuclear forensic. This study aims to expand the traditional characterization analytical techniques by measuring the oxygen isotopic composition of various uranium oxides (e.g., $ UO_{2} $, $ U_{3} %$ O_{8} $), uranium ore concentrates (UOC). We apply it to $ UO_{2} $ pellets from the Fifth Collaborative Materials Exercise (CMX-5). We developed an accurate laser fluorination in line with continuous-flow mass spectrometry analytical method for measuring oxygen isotopes in sub-milligram nuclear materials, including raw materials and selected materials from several stages of the fuel production cycle. We report for the first time, on the oxygen isotope composition of the two $ UO_{2} $ fuel pellets, used for the international CMX-5. We show that $ δ^{18} $O of these pellets differ by 1.7‰, which probably originates from their manufacturing processes. CUP-2, a UOC, was used to demonstrate the challenge of measuring isotope composition of hydrated forms of uranium oxides. $ U_{3} %$ O_{8} $ was found to exhibit lower than expected, by stoichiometric formula, oxygen contents. That might originate from oxygen loss during the pre-fluorination process, or indicates the presence of more than one phase within this particular $ U_{3} %$ O_{8} $ system. © Akadémiai Kiadó, Budapest, Hungary 2021 |
abstractGer |
Abstract Uranium oxides are essential materials in the production process of nuclear fuel for civilian or military applications. As such, identifying their geological origin, manufacturing process and age, plays a central role in the field of nuclear forensic. This study aims to expand the traditional characterization analytical techniques by measuring the oxygen isotopic composition of various uranium oxides (e.g., $ UO_{2} $, $ U_{3} %$ O_{8} $), uranium ore concentrates (UOC). We apply it to $ UO_{2} $ pellets from the Fifth Collaborative Materials Exercise (CMX-5). We developed an accurate laser fluorination in line with continuous-flow mass spectrometry analytical method for measuring oxygen isotopes in sub-milligram nuclear materials, including raw materials and selected materials from several stages of the fuel production cycle. We report for the first time, on the oxygen isotope composition of the two $ UO_{2} $ fuel pellets, used for the international CMX-5. We show that $ δ^{18} $O of these pellets differ by 1.7‰, which probably originates from their manufacturing processes. CUP-2, a UOC, was used to demonstrate the challenge of measuring isotope composition of hydrated forms of uranium oxides. $ U_{3} %$ O_{8} $ was found to exhibit lower than expected, by stoichiometric formula, oxygen contents. That might originate from oxygen loss during the pre-fluorination process, or indicates the presence of more than one phase within this particular $ U_{3} %$ O_{8} $ system. © Akadémiai Kiadó, Budapest, Hungary 2021 |
abstract_unstemmed |
Abstract Uranium oxides are essential materials in the production process of nuclear fuel for civilian or military applications. As such, identifying their geological origin, manufacturing process and age, plays a central role in the field of nuclear forensic. This study aims to expand the traditional characterization analytical techniques by measuring the oxygen isotopic composition of various uranium oxides (e.g., $ UO_{2} $, $ U_{3} %$ O_{8} $), uranium ore concentrates (UOC). We apply it to $ UO_{2} $ pellets from the Fifth Collaborative Materials Exercise (CMX-5). We developed an accurate laser fluorination in line with continuous-flow mass spectrometry analytical method for measuring oxygen isotopes in sub-milligram nuclear materials, including raw materials and selected materials from several stages of the fuel production cycle. We report for the first time, on the oxygen isotope composition of the two $ UO_{2} $ fuel pellets, used for the international CMX-5. We show that $ δ^{18} $O of these pellets differ by 1.7‰, which probably originates from their manufacturing processes. CUP-2, a UOC, was used to demonstrate the challenge of measuring isotope composition of hydrated forms of uranium oxides. $ U_{3} %$ O_{8} $ was found to exhibit lower than expected, by stoichiometric formula, oxygen contents. That might originate from oxygen loss during the pre-fluorination process, or indicates the presence of more than one phase within this particular $ U_{3} %$ O_{8} $ system. © Akadémiai Kiadó, Budapest, Hungary 2021 |
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Oxygen isotopes of fuel pellets from the fifth collaborative materials exercise and uranium oxides reference materials determined by continuous flow laser fluorination mass spectrometry for nuclear forensic applications |
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https://dx.doi.org/10.1007/s10967-021-07858-x |
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score |
7.4011316 |