Evolution of structures and internal stress of ZrC-SiC composite under He ion irradiation and post-annealing
Composite ceramics show great potential for utilization in nuclear systems. However, the component phases therein may exhibit large variations in structural response to the ion irradiation including degree of lattice expansion, ability to maintain the crystallinity, types and density of as-formed de...
Ausführliche Beschreibung
Autor*in: |
Bao, Weichao [verfasserIn] Wang, Xin-Gang [verfasserIn] Lu, Ying [verfasserIn] Sun, Shikuan [verfasserIn] Wang, Xiaofei [verfasserIn] Xin, Xiao-Ting [verfasserIn] Zhang, Guo-Jun [verfasserIn] Xu, Fangfang [verfasserIn] |
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E-Artikel |
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Sprache: |
Englisch |
Erschienen: |
2023 |
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Schlagwörter: |
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Übergeordnetes Werk: |
Enthalten in: Materials characterization - New York, NY : Science Direct, 1990, 207 |
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Übergeordnetes Werk: |
volume:207 |
DOI / URN: |
10.1016/j.matchar.2023.113515 |
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Katalog-ID: |
ELV06642383X |
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520 | |a Composite ceramics show great potential for utilization in nuclear systems. However, the component phases therein may exhibit large variations in structural response to the ion irradiation including degree of lattice expansion, ability to maintain the crystallinity, types and density of as-formed defects, etc. Such discrepancy may result in the evolution of internal stress and consequently more complicated interactions with respect to the irradiation behavior, which remains less understood. In this study, a ZrC–30 vol% SiC composite is chosen to study the irradiation and helium retention behavior under 540 keV He ion irradiation with a fluence of 1 × 1017/cm2 and subsequent annealing at 1000 °C and 1500 °C. Irradiation-induced volume dilation of ZrC lattice and especially from an amorphization process of SiC leads to a maximum compressive stress of ∼66 GPa at a certain irradiation depth, at which horizontal cracks are generated but only in ZrC grains. During high-temperature annealing, migration of defects, diffusion and coalesce of helium species, growth of He bubbles, recovery of crystal lattices and formation of dislocations are found to be closely correlated to the irradiation-induced gradient of helium retention concentration, lattice damage and internal stress along the irradiation depth along with the recrystallization process of amorphous SiC. The as-observed irradiation behavior and structural evolution during annealing are discussed by theoretical consideration of internal stress in the composite using the COMSOL Multiphysics package. | ||
650 | 4 | |a ZrC-SiC composite | |
650 | 4 | |a He ion irradiation | |
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700 | 1 | |a Wang, Xin-Gang |e verfasserin |4 aut | |
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700 | 1 | |a Wang, Xiaofei |e verfasserin |4 aut | |
700 | 1 | |a Xin, Xiao-Ting |e verfasserin |4 aut | |
700 | 1 | |a Zhang, Guo-Jun |e verfasserin |4 aut | |
700 | 1 | |a Xu, Fangfang |e verfasserin |4 aut | |
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10.1016/j.matchar.2023.113515 doi (DE-627)ELV06642383X (ELSEVIER)S1044-5803(23)00874-4 DE-627 ger DE-627 rda eng 670 VZ 51.30 bkl Bao, Weichao verfasserin aut Evolution of structures and internal stress of ZrC-SiC composite under He ion irradiation and post-annealing 2023 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Composite ceramics show great potential for utilization in nuclear systems. However, the component phases therein may exhibit large variations in structural response to the ion irradiation including degree of lattice expansion, ability to maintain the crystallinity, types and density of as-formed defects, etc. Such discrepancy may result in the evolution of internal stress and consequently more complicated interactions with respect to the irradiation behavior, which remains less understood. In this study, a ZrC–30 vol% SiC composite is chosen to study the irradiation and helium retention behavior under 540 keV He ion irradiation with a fluence of 1 × 1017/cm2 and subsequent annealing at 1000 °C and 1500 °C. Irradiation-induced volume dilation of ZrC lattice and especially from an amorphization process of SiC leads to a maximum compressive stress of ∼66 GPa at a certain irradiation depth, at which horizontal cracks are generated but only in ZrC grains. During high-temperature annealing, migration of defects, diffusion and coalesce of helium species, growth of He bubbles, recovery of crystal lattices and formation of dislocations are found to be closely correlated to the irradiation-induced gradient of helium retention concentration, lattice damage and internal stress along the irradiation depth along with the recrystallization process of amorphous SiC. The as-observed irradiation behavior and structural evolution during annealing are discussed by theoretical consideration of internal stress in the composite using the COMSOL Multiphysics package. ZrC-SiC composite He ion irradiation Internal stress Helium retention behavior Dislocations Wang, Xin-Gang verfasserin aut Lu, Ying verfasserin aut Sun, Shikuan verfasserin aut Wang, Xiaofei verfasserin aut Xin, Xiao-Ting verfasserin aut Zhang, Guo-Jun verfasserin aut Xu, Fangfang verfasserin aut Enthalten in Materials characterization New York, NY : Science Direct, 1990 207 Online-Ressource (DE-627)302719288 (DE-600)1491951-5 (DE-576)259483966 nnns volume:207 GBV_USEFLAG_U GBV_ELV SYSFLAG_U GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 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_2034 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2088 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 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_4333 GBV_ILN_4334 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 51.30 Werkstoffprüfung Werkstoffuntersuchung VZ AR 207 |
spelling |
10.1016/j.matchar.2023.113515 doi (DE-627)ELV06642383X (ELSEVIER)S1044-5803(23)00874-4 DE-627 ger DE-627 rda eng 670 VZ 51.30 bkl Bao, Weichao verfasserin aut Evolution of structures and internal stress of ZrC-SiC composite under He ion irradiation and post-annealing 2023 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Composite ceramics show great potential for utilization in nuclear systems. However, the component phases therein may exhibit large variations in structural response to the ion irradiation including degree of lattice expansion, ability to maintain the crystallinity, types and density of as-formed defects, etc. Such discrepancy may result in the evolution of internal stress and consequently more complicated interactions with respect to the irradiation behavior, which remains less understood. In this study, a ZrC–30 vol% SiC composite is chosen to study the irradiation and helium retention behavior under 540 keV He ion irradiation with a fluence of 1 × 1017/cm2 and subsequent annealing at 1000 °C and 1500 °C. Irradiation-induced volume dilation of ZrC lattice and especially from an amorphization process of SiC leads to a maximum compressive stress of ∼66 GPa at a certain irradiation depth, at which horizontal cracks are generated but only in ZrC grains. During high-temperature annealing, migration of defects, diffusion and coalesce of helium species, growth of He bubbles, recovery of crystal lattices and formation of dislocations are found to be closely correlated to the irradiation-induced gradient of helium retention concentration, lattice damage and internal stress along the irradiation depth along with the recrystallization process of amorphous SiC. The as-observed irradiation behavior and structural evolution during annealing are discussed by theoretical consideration of internal stress in the composite using the COMSOL Multiphysics package. ZrC-SiC composite He ion irradiation Internal stress Helium retention behavior Dislocations Wang, Xin-Gang verfasserin aut Lu, Ying verfasserin aut Sun, Shikuan verfasserin aut Wang, Xiaofei verfasserin aut Xin, Xiao-Ting verfasserin aut Zhang, Guo-Jun verfasserin aut Xu, Fangfang verfasserin aut Enthalten in Materials characterization New York, NY : Science Direct, 1990 207 Online-Ressource (DE-627)302719288 (DE-600)1491951-5 (DE-576)259483966 nnns volume:207 GBV_USEFLAG_U GBV_ELV SYSFLAG_U GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 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_2034 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2088 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 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_4333 GBV_ILN_4334 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 51.30 Werkstoffprüfung Werkstoffuntersuchung VZ AR 207 |
allfields_unstemmed |
10.1016/j.matchar.2023.113515 doi (DE-627)ELV06642383X (ELSEVIER)S1044-5803(23)00874-4 DE-627 ger DE-627 rda eng 670 VZ 51.30 bkl Bao, Weichao verfasserin aut Evolution of structures and internal stress of ZrC-SiC composite under He ion irradiation and post-annealing 2023 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Composite ceramics show great potential for utilization in nuclear systems. However, the component phases therein may exhibit large variations in structural response to the ion irradiation including degree of lattice expansion, ability to maintain the crystallinity, types and density of as-formed defects, etc. Such discrepancy may result in the evolution of internal stress and consequently more complicated interactions with respect to the irradiation behavior, which remains less understood. In this study, a ZrC–30 vol% SiC composite is chosen to study the irradiation and helium retention behavior under 540 keV He ion irradiation with a fluence of 1 × 1017/cm2 and subsequent annealing at 1000 °C and 1500 °C. Irradiation-induced volume dilation of ZrC lattice and especially from an amorphization process of SiC leads to a maximum compressive stress of ∼66 GPa at a certain irradiation depth, at which horizontal cracks are generated but only in ZrC grains. During high-temperature annealing, migration of defects, diffusion and coalesce of helium species, growth of He bubbles, recovery of crystal lattices and formation of dislocations are found to be closely correlated to the irradiation-induced gradient of helium retention concentration, lattice damage and internal stress along the irradiation depth along with the recrystallization process of amorphous SiC. The as-observed irradiation behavior and structural evolution during annealing are discussed by theoretical consideration of internal stress in the composite using the COMSOL Multiphysics package. ZrC-SiC composite He ion irradiation Internal stress Helium retention behavior Dislocations Wang, Xin-Gang verfasserin aut Lu, Ying verfasserin aut Sun, Shikuan verfasserin aut Wang, Xiaofei verfasserin aut Xin, Xiao-Ting verfasserin aut Zhang, Guo-Jun verfasserin aut Xu, Fangfang verfasserin aut Enthalten in Materials characterization New York, NY : Science Direct, 1990 207 Online-Ressource (DE-627)302719288 (DE-600)1491951-5 (DE-576)259483966 nnns volume:207 GBV_USEFLAG_U GBV_ELV SYSFLAG_U GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 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_2034 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2088 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 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_4333 GBV_ILN_4334 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 51.30 Werkstoffprüfung Werkstoffuntersuchung VZ AR 207 |
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10.1016/j.matchar.2023.113515 doi (DE-627)ELV06642383X (ELSEVIER)S1044-5803(23)00874-4 DE-627 ger DE-627 rda eng 670 VZ 51.30 bkl Bao, Weichao verfasserin aut Evolution of structures and internal stress of ZrC-SiC composite under He ion irradiation and post-annealing 2023 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Composite ceramics show great potential for utilization in nuclear systems. However, the component phases therein may exhibit large variations in structural response to the ion irradiation including degree of lattice expansion, ability to maintain the crystallinity, types and density of as-formed defects, etc. Such discrepancy may result in the evolution of internal stress and consequently more complicated interactions with respect to the irradiation behavior, which remains less understood. In this study, a ZrC–30 vol% SiC composite is chosen to study the irradiation and helium retention behavior under 540 keV He ion irradiation with a fluence of 1 × 1017/cm2 and subsequent annealing at 1000 °C and 1500 °C. Irradiation-induced volume dilation of ZrC lattice and especially from an amorphization process of SiC leads to a maximum compressive stress of ∼66 GPa at a certain irradiation depth, at which horizontal cracks are generated but only in ZrC grains. During high-temperature annealing, migration of defects, diffusion and coalesce of helium species, growth of He bubbles, recovery of crystal lattices and formation of dislocations are found to be closely correlated to the irradiation-induced gradient of helium retention concentration, lattice damage and internal stress along the irradiation depth along with the recrystallization process of amorphous SiC. The as-observed irradiation behavior and structural evolution during annealing are discussed by theoretical consideration of internal stress in the composite using the COMSOL Multiphysics package. ZrC-SiC composite He ion irradiation Internal stress Helium retention behavior Dislocations Wang, Xin-Gang verfasserin aut Lu, Ying verfasserin aut Sun, Shikuan verfasserin aut Wang, Xiaofei verfasserin aut Xin, Xiao-Ting verfasserin aut Zhang, Guo-Jun verfasserin aut Xu, Fangfang verfasserin aut Enthalten in Materials characterization New York, NY : Science Direct, 1990 207 Online-Ressource (DE-627)302719288 (DE-600)1491951-5 (DE-576)259483966 nnns volume:207 GBV_USEFLAG_U GBV_ELV SYSFLAG_U GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 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_2034 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2088 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 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_4333 GBV_ILN_4334 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 51.30 Werkstoffprüfung Werkstoffuntersuchung VZ AR 207 |
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10.1016/j.matchar.2023.113515 doi (DE-627)ELV06642383X (ELSEVIER)S1044-5803(23)00874-4 DE-627 ger DE-627 rda eng 670 VZ 51.30 bkl Bao, Weichao verfasserin aut Evolution of structures and internal stress of ZrC-SiC composite under He ion irradiation and post-annealing 2023 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Composite ceramics show great potential for utilization in nuclear systems. However, the component phases therein may exhibit large variations in structural response to the ion irradiation including degree of lattice expansion, ability to maintain the crystallinity, types and density of as-formed defects, etc. Such discrepancy may result in the evolution of internal stress and consequently more complicated interactions with respect to the irradiation behavior, which remains less understood. In this study, a ZrC–30 vol% SiC composite is chosen to study the irradiation and helium retention behavior under 540 keV He ion irradiation with a fluence of 1 × 1017/cm2 and subsequent annealing at 1000 °C and 1500 °C. Irradiation-induced volume dilation of ZrC lattice and especially from an amorphization process of SiC leads to a maximum compressive stress of ∼66 GPa at a certain irradiation depth, at which horizontal cracks are generated but only in ZrC grains. During high-temperature annealing, migration of defects, diffusion and coalesce of helium species, growth of He bubbles, recovery of crystal lattices and formation of dislocations are found to be closely correlated to the irradiation-induced gradient of helium retention concentration, lattice damage and internal stress along the irradiation depth along with the recrystallization process of amorphous SiC. The as-observed irradiation behavior and structural evolution during annealing are discussed by theoretical consideration of internal stress in the composite using the COMSOL Multiphysics package. ZrC-SiC composite He ion irradiation Internal stress Helium retention behavior Dislocations Wang, Xin-Gang verfasserin aut Lu, Ying verfasserin aut Sun, Shikuan verfasserin aut Wang, Xiaofei verfasserin aut Xin, Xiao-Ting verfasserin aut Zhang, Guo-Jun verfasserin aut Xu, Fangfang verfasserin aut Enthalten in Materials characterization New York, NY : Science Direct, 1990 207 Online-Ressource (DE-627)302719288 (DE-600)1491951-5 (DE-576)259483966 nnns volume:207 GBV_USEFLAG_U GBV_ELV SYSFLAG_U GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 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_2034 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2088 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 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_4333 GBV_ILN_4334 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 51.30 Werkstoffprüfung Werkstoffuntersuchung VZ AR 207 |
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ZrC-SiC composite He ion irradiation Internal stress Helium retention behavior Dislocations |
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Bao, Weichao @@aut@@ Wang, Xin-Gang @@aut@@ Lu, Ying @@aut@@ Sun, Shikuan @@aut@@ Wang, Xiaofei @@aut@@ Xin, Xiao-Ting @@aut@@ Zhang, Guo-Jun @@aut@@ Xu, Fangfang @@aut@@ |
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Bao, Weichao |
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Bao, Weichao ddc 670 bkl 51.30 misc ZrC-SiC composite misc He ion irradiation misc Internal stress misc Helium retention behavior misc Dislocations Evolution of structures and internal stress of ZrC-SiC composite under He ion irradiation and post-annealing |
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670 VZ 51.30 bkl Evolution of structures and internal stress of ZrC-SiC composite under He ion irradiation and post-annealing ZrC-SiC composite He ion irradiation Internal stress Helium retention behavior Dislocations |
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ddc 670 bkl 51.30 misc ZrC-SiC composite misc He ion irradiation misc Internal stress misc Helium retention behavior misc Dislocations |
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ddc 670 bkl 51.30 misc ZrC-SiC composite misc He ion irradiation misc Internal stress misc Helium retention behavior misc Dislocations |
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Evolution of structures and internal stress of ZrC-SiC composite under He ion irradiation and post-annealing |
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Evolution of structures and internal stress of ZrC-SiC composite under He ion irradiation and post-annealing |
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evolution of structures and internal stress of zrc-sic composite under he ion irradiation and post-annealing |
title_auth |
Evolution of structures and internal stress of ZrC-SiC composite under He ion irradiation and post-annealing |
abstract |
Composite ceramics show great potential for utilization in nuclear systems. However, the component phases therein may exhibit large variations in structural response to the ion irradiation including degree of lattice expansion, ability to maintain the crystallinity, types and density of as-formed defects, etc. Such discrepancy may result in the evolution of internal stress and consequently more complicated interactions with respect to the irradiation behavior, which remains less understood. In this study, a ZrC–30 vol% SiC composite is chosen to study the irradiation and helium retention behavior under 540 keV He ion irradiation with a fluence of 1 × 1017/cm2 and subsequent annealing at 1000 °C and 1500 °C. Irradiation-induced volume dilation of ZrC lattice and especially from an amorphization process of SiC leads to a maximum compressive stress of ∼66 GPa at a certain irradiation depth, at which horizontal cracks are generated but only in ZrC grains. During high-temperature annealing, migration of defects, diffusion and coalesce of helium species, growth of He bubbles, recovery of crystal lattices and formation of dislocations are found to be closely correlated to the irradiation-induced gradient of helium retention concentration, lattice damage and internal stress along the irradiation depth along with the recrystallization process of amorphous SiC. The as-observed irradiation behavior and structural evolution during annealing are discussed by theoretical consideration of internal stress in the composite using the COMSOL Multiphysics package. |
abstractGer |
Composite ceramics show great potential for utilization in nuclear systems. However, the component phases therein may exhibit large variations in structural response to the ion irradiation including degree of lattice expansion, ability to maintain the crystallinity, types and density of as-formed defects, etc. Such discrepancy may result in the evolution of internal stress and consequently more complicated interactions with respect to the irradiation behavior, which remains less understood. In this study, a ZrC–30 vol% SiC composite is chosen to study the irradiation and helium retention behavior under 540 keV He ion irradiation with a fluence of 1 × 1017/cm2 and subsequent annealing at 1000 °C and 1500 °C. Irradiation-induced volume dilation of ZrC lattice and especially from an amorphization process of SiC leads to a maximum compressive stress of ∼66 GPa at a certain irradiation depth, at which horizontal cracks are generated but only in ZrC grains. During high-temperature annealing, migration of defects, diffusion and coalesce of helium species, growth of He bubbles, recovery of crystal lattices and formation of dislocations are found to be closely correlated to the irradiation-induced gradient of helium retention concentration, lattice damage and internal stress along the irradiation depth along with the recrystallization process of amorphous SiC. The as-observed irradiation behavior and structural evolution during annealing are discussed by theoretical consideration of internal stress in the composite using the COMSOL Multiphysics package. |
abstract_unstemmed |
Composite ceramics show great potential for utilization in nuclear systems. However, the component phases therein may exhibit large variations in structural response to the ion irradiation including degree of lattice expansion, ability to maintain the crystallinity, types and density of as-formed defects, etc. Such discrepancy may result in the evolution of internal stress and consequently more complicated interactions with respect to the irradiation behavior, which remains less understood. In this study, a ZrC–30 vol% SiC composite is chosen to study the irradiation and helium retention behavior under 540 keV He ion irradiation with a fluence of 1 × 1017/cm2 and subsequent annealing at 1000 °C and 1500 °C. Irradiation-induced volume dilation of ZrC lattice and especially from an amorphization process of SiC leads to a maximum compressive stress of ∼66 GPa at a certain irradiation depth, at which horizontal cracks are generated but only in ZrC grains. During high-temperature annealing, migration of defects, diffusion and coalesce of helium species, growth of He bubbles, recovery of crystal lattices and formation of dislocations are found to be closely correlated to the irradiation-induced gradient of helium retention concentration, lattice damage and internal stress along the irradiation depth along with the recrystallization process of amorphous SiC. The as-observed irradiation behavior and structural evolution during annealing are discussed by theoretical consideration of internal stress in the composite using the COMSOL Multiphysics package. |
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title_short |
Evolution of structures and internal stress of ZrC-SiC composite under He ion irradiation and post-annealing |
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Wang, Xin-Gang Lu, Ying Sun, Shikuan Wang, Xiaofei Xin, Xiao-Ting Zhang, Guo-Jun Xu, Fangfang |
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|
score |
7.4000044 |