Carbonate of strontium anchored at the edge of graphite
With the continuous growth of the fourth-generation nuclear reactor, the oxidation of irradiated graphite (i-graphite) has become a great concern worldwide in recent years, not only for the far-reaching significance in the treatment of i-graphite waste, but also for the safety evaluation of the reac...
| Main Authors: | , , , , , , , , , |
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| Format: | Article |
| Language: | English |
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Elsevier
2023-06-01
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| Series: | Nuclear Materials and Energy |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S235217912300087X |
| _version_ | 1797801055315034112 |
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| author | Wei Zhang Hongwei Zhu Zelin Gao Taowei Wang Wendurina Gang Xu Shu-Xian Hu Xiaotong Chen Bing Liu Yaping Tang |
| author_facet | Wei Zhang Hongwei Zhu Zelin Gao Taowei Wang Wendurina Gang Xu Shu-Xian Hu Xiaotong Chen Bing Liu Yaping Tang |
| author_sort | Wei Zhang |
| collection | DOAJ |
| description | With the continuous growth of the fourth-generation nuclear reactor, the oxidation of irradiated graphite (i-graphite) has become a great concern worldwide in recent years, not only for the far-reaching significance in the treatment of i-graphite waste, but also for the safety evaluation of the reactor. Fission products (FPs) and activation of impurities are generated in i-graphite during reactor operation and inevitably released as radioactive dust when i-graphite is oxidized. The investigation of the binding mechanism between nuclides and graphite dust is vital for further separating procedures of off-gas decontamination. Herein, the mechanism of FP release during the oxidation of High-Temperature Gas-Cooled Reactors’ matrix graphite was explored with Strontium (Sr) as an example. The Sr-loaded matrix graphite was prepared by impregnation and characterized by secondary ion mass spectrometry (SIMS), X-ray powder diffraction (XRD), scanning electron microscope-energy dispersive spectrometer (SEM-EDS), and Raman spectra. The released Sr chemical speciation was extrapolated as SrCO3 through the investigation of the temperature and air flow rate effects on oxidation products. Additionally, the main morphology of the released fragment was identified as SrCO3 clusters anchored at the edge of graphite. The ab initio calculations revealed the mechanism for the anchoring of SrCO3 at the edge of graphite via adsorption. These findings provide a novel understanding of Sr-releasing behavior when i-graphite is oxidized. |
| first_indexed | 2024-03-13T04:44:35Z |
| format | Article |
| id | doaj.art-8ebe80fdba9b416d8407fb4203151935 |
| institution | Directory Open Access Journal |
| issn | 2352-1791 |
| language | English |
| last_indexed | 2024-03-13T04:44:35Z |
| publishDate | 2023-06-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Materials and Energy |
| spelling | doaj.art-8ebe80fdba9b416d8407fb42031519352023-06-19T04:28:53ZengElsevierNuclear Materials and Energy2352-17912023-06-0135101448Carbonate of strontium anchored at the edge of graphiteWei Zhang0Hongwei Zhu1Zelin Gao2Taowei Wang3 Wendurina4Gang Xu5Shu-Xian Hu6Xiaotong Chen7Bing Liu8Yaping Tang9Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Tsinghua University, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Tsinghua University, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Tsinghua University, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Tsinghua University, Beijing 100084, ChinaDepartment of Physics, University of Science and Technology Beijing, Beijing 100083, ChinaInstitute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Tsinghua University, Beijing 100084, ChinaDepartment of Physics, University of Science and Technology Beijing, Beijing 100083, China; Corresponding authors.Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Tsinghua University, Beijing 100084, China; Corresponding authors.Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Tsinghua University, Beijing 100084, China; Corresponding authors.Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Tsinghua University, Beijing 100084, ChinaWith the continuous growth of the fourth-generation nuclear reactor, the oxidation of irradiated graphite (i-graphite) has become a great concern worldwide in recent years, not only for the far-reaching significance in the treatment of i-graphite waste, but also for the safety evaluation of the reactor. Fission products (FPs) and activation of impurities are generated in i-graphite during reactor operation and inevitably released as radioactive dust when i-graphite is oxidized. The investigation of the binding mechanism between nuclides and graphite dust is vital for further separating procedures of off-gas decontamination. Herein, the mechanism of FP release during the oxidation of High-Temperature Gas-Cooled Reactors’ matrix graphite was explored with Strontium (Sr) as an example. The Sr-loaded matrix graphite was prepared by impregnation and characterized by secondary ion mass spectrometry (SIMS), X-ray powder diffraction (XRD), scanning electron microscope-energy dispersive spectrometer (SEM-EDS), and Raman spectra. The released Sr chemical speciation was extrapolated as SrCO3 through the investigation of the temperature and air flow rate effects on oxidation products. Additionally, the main morphology of the released fragment was identified as SrCO3 clusters anchored at the edge of graphite. The ab initio calculations revealed the mechanism for the anchoring of SrCO3 at the edge of graphite via adsorption. These findings provide a novel understanding of Sr-releasing behavior when i-graphite is oxidized.http://www.sciencedirect.com/science/article/pii/S235217912300087XStrontiumIrradiated nuclear graphiteHigh-temperature oxidationReleaseGraphite edge |
| spellingShingle | Wei Zhang Hongwei Zhu Zelin Gao Taowei Wang Wendurina Gang Xu Shu-Xian Hu Xiaotong Chen Bing Liu Yaping Tang Carbonate of strontium anchored at the edge of graphite Nuclear Materials and Energy Strontium Irradiated nuclear graphite High-temperature oxidation Release Graphite edge |
| title | Carbonate of strontium anchored at the edge of graphite |
| title_full | Carbonate of strontium anchored at the edge of graphite |
| title_fullStr | Carbonate of strontium anchored at the edge of graphite |
| title_full_unstemmed | Carbonate of strontium anchored at the edge of graphite |
| title_short | Carbonate of strontium anchored at the edge of graphite |
| title_sort | carbonate of strontium anchored at the edge of graphite |
| topic | Strontium Irradiated nuclear graphite High-temperature oxidation Release Graphite edge |
| url | http://www.sciencedirect.com/science/article/pii/S235217912300087X |
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