Investigation of ion irradiation hardening behaviors of tempered and long-term thermal aged T92 steel

9Cr ferritic/martensitic steels are promising materials for in-core components in advanced Gen-IV reactors. In these applications, their long-term microstructural stability under thermal exposure and resistance to neutron irradiation are essential. Tempered (unaged) and long-term thermal aged T92 sa...
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Gespeichert in:

Autor*in:	Zhao, Dandan [verfasserIn] Li, Shilei [verfasserIn] Wang, Yanli [verfasserIn] Liu, Fang [verfasserIn] Wang, Xitao [verfasserIn]

Format:	E-Artikel
Sprache:	Englisch

Erschienen:	2018

Schlagwörter:	Ferritic/martensitic steels Ion irradiation Thermal aging Irradiation hardening

Übergeordnetes Werk:	Enthalten in: Journal of nuclear materials - Amsterdam [u.a.] : Elsevier Science, 1959, 511, Seite 191-199
Übergeordnetes Werk:	volume:511 ; pages:191-199

DOI / URN:	10.1016/j.jnucmat.2018.09.016

Katalog-ID:	ELV000952109

Internformat


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520			\|a 9Cr ferritic/martensitic steels are promising materials for in-core components in advanced Gen-IV reactors. In these applications, their long-term microstructural stability under thermal exposure and resistance to neutron irradiation are essential. Tempered (unaged) and long-term thermal aged T92 samples were used to evaluate the effects of thermal aging and ion irradiation on the microstructure and micromechanical properties of the steel. Both the tempered and aged samples were irradiated with 3 MeV Fe11+ ions to 0.25, 0.50, 1.00 and 5.00 dpa at room temperature. Using the nanoindentation technique, the irradiation hardening behaviors of T92 steel were investigated. The irradiation hardening effect was observed in both the tempered and aged T92 samples. To eliminate the soft substrate effect, the critical indentation depth was determined using the ratio of the average hardness of irradiated and unirradiated samples at the same depth. Under the same irradiation conditions, the macroscopic hardness values of the aged T92 samples after irradiation were lower than those of the tempered samples. The irradiation hardening effect was more significant in the aged T92 due to the decreased dislocation density and the coarsened martensitic lath after long-term thermal aging.
650		4	\|a Ferritic/martensitic steels
650		4	\|a Ion irradiation
650		4	\|a Thermal aging
650		4	\|a Irradiation hardening
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700	1		\|a Liu, Fang \|e verfasserin \|0 (orcid)0000-0002-3468-4450 \|4 aut
700	1		\|a Wang, Xitao \|e verfasserin \|0 (orcid)0000-0002-1138-3372 \|4 aut
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publishDate	2018
allfields	10.1016/j.jnucmat.2018.09.016 doi (DE-627)ELV000952109 (ELSEVIER)S0022-3115(18)30794-3 DE-627 ger DE-627 rda eng 530 620 DE-600 51.40 bkl 52.55 bkl 33.81 bkl 33.80 bkl Zhao, Dandan verfasserin aut Investigation of ion irradiation hardening behaviors of tempered and long-term thermal aged T92 steel 2018 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier 9Cr ferritic/martensitic steels are promising materials for in-core components in advanced Gen-IV reactors. In these applications, their long-term microstructural stability under thermal exposure and resistance to neutron irradiation are essential. Tempered (unaged) and long-term thermal aged T92 samples were used to evaluate the effects of thermal aging and ion irradiation on the microstructure and micromechanical properties of the steel. Both the tempered and aged samples were irradiated with 3 MeV Fe11+ ions to 0.25, 0.50, 1.00 and 5.00 dpa at room temperature. Using the nanoindentation technique, the irradiation hardening behaviors of T92 steel were investigated. The irradiation hardening effect was observed in both the tempered and aged T92 samples. To eliminate the soft substrate effect, the critical indentation depth was determined using the ratio of the average hardness of irradiated and unirradiated samples at the same depth. Under the same irradiation conditions, the macroscopic hardness values of the aged T92 samples after irradiation were lower than those of the tempered samples. The irradiation hardening effect was more significant in the aged T92 due to the decreased dislocation density and the coarsened martensitic lath after long-term thermal aging. Ferritic/martensitic steels Ion irradiation Thermal aging Irradiation hardening Li, Shilei verfasserin (orcid)0000-0001-5432-9475 aut Wang, Yanli verfasserin (orcid)0000-0003-1284-1547 aut Liu, Fang verfasserin (orcid)0000-0002-3468-4450 aut Wang, Xitao verfasserin (orcid)0000-0002-1138-3372 aut Enthalten in Journal of nuclear materials Amsterdam [u.a.] : Elsevier Science, 1959 511, Seite 191-199 Online-Ressource (DE-627)320410730 (DE-600)2001279-2 (DE-576)251938174 nnns volume:511 pages:191-199 GBV_USEFLAG_U SYSFLAG_U GBV_ELV 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_63 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_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_224 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2336 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4313 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4393 51.40 Werkstoffe für bestimmte Anwendungsgebiete 52.55 Kerntechnik Reaktortechnik 33.81 Kernfusion 33.80 Plasmaphysik AR 511 191-199
spelling	10.1016/j.jnucmat.2018.09.016 doi (DE-627)ELV000952109 (ELSEVIER)S0022-3115(18)30794-3 DE-627 ger DE-627 rda eng 530 620 DE-600 51.40 bkl 52.55 bkl 33.81 bkl 33.80 bkl Zhao, Dandan verfasserin aut Investigation of ion irradiation hardening behaviors of tempered and long-term thermal aged T92 steel 2018 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier 9Cr ferritic/martensitic steels are promising materials for in-core components in advanced Gen-IV reactors. In these applications, their long-term microstructural stability under thermal exposure and resistance to neutron irradiation are essential. Tempered (unaged) and long-term thermal aged T92 samples were used to evaluate the effects of thermal aging and ion irradiation on the microstructure and micromechanical properties of the steel. Both the tempered and aged samples were irradiated with 3 MeV Fe11+ ions to 0.25, 0.50, 1.00 and 5.00 dpa at room temperature. Using the nanoindentation technique, the irradiation hardening behaviors of T92 steel were investigated. The irradiation hardening effect was observed in both the tempered and aged T92 samples. To eliminate the soft substrate effect, the critical indentation depth was determined using the ratio of the average hardness of irradiated and unirradiated samples at the same depth. Under the same irradiation conditions, the macroscopic hardness values of the aged T92 samples after irradiation were lower than those of the tempered samples. The irradiation hardening effect was more significant in the aged T92 due to the decreased dislocation density and the coarsened martensitic lath after long-term thermal aging. Ferritic/martensitic steels Ion irradiation Thermal aging Irradiation hardening Li, Shilei verfasserin (orcid)0000-0001-5432-9475 aut Wang, Yanli verfasserin (orcid)0000-0003-1284-1547 aut Liu, Fang verfasserin (orcid)0000-0002-3468-4450 aut Wang, Xitao verfasserin (orcid)0000-0002-1138-3372 aut Enthalten in Journal of nuclear materials Amsterdam [u.a.] : Elsevier Science, 1959 511, Seite 191-199 Online-Ressource (DE-627)320410730 (DE-600)2001279-2 (DE-576)251938174 nnns volume:511 pages:191-199 GBV_USEFLAG_U SYSFLAG_U GBV_ELV 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_63 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_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_224 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2336 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4313 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4393 51.40 Werkstoffe für bestimmte Anwendungsgebiete 52.55 Kerntechnik Reaktortechnik 33.81 Kernfusion 33.80 Plasmaphysik AR 511 191-199
allfields_unstemmed	10.1016/j.jnucmat.2018.09.016 doi (DE-627)ELV000952109 (ELSEVIER)S0022-3115(18)30794-3 DE-627 ger DE-627 rda eng 530 620 DE-600 51.40 bkl 52.55 bkl 33.81 bkl 33.80 bkl Zhao, Dandan verfasserin aut Investigation of ion irradiation hardening behaviors of tempered and long-term thermal aged T92 steel 2018 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier 9Cr ferritic/martensitic steels are promising materials for in-core components in advanced Gen-IV reactors. In these applications, their long-term microstructural stability under thermal exposure and resistance to neutron irradiation are essential. Tempered (unaged) and long-term thermal aged T92 samples were used to evaluate the effects of thermal aging and ion irradiation on the microstructure and micromechanical properties of the steel. Both the tempered and aged samples were irradiated with 3 MeV Fe11+ ions to 0.25, 0.50, 1.00 and 5.00 dpa at room temperature. Using the nanoindentation technique, the irradiation hardening behaviors of T92 steel were investigated. The irradiation hardening effect was observed in both the tempered and aged T92 samples. To eliminate the soft substrate effect, the critical indentation depth was determined using the ratio of the average hardness of irradiated and unirradiated samples at the same depth. Under the same irradiation conditions, the macroscopic hardness values of the aged T92 samples after irradiation were lower than those of the tempered samples. The irradiation hardening effect was more significant in the aged T92 due to the decreased dislocation density and the coarsened martensitic lath after long-term thermal aging. Ferritic/martensitic steels Ion irradiation Thermal aging Irradiation hardening Li, Shilei verfasserin (orcid)0000-0001-5432-9475 aut Wang, Yanli verfasserin (orcid)0000-0003-1284-1547 aut Liu, Fang verfasserin (orcid)0000-0002-3468-4450 aut Wang, Xitao verfasserin (orcid)0000-0002-1138-3372 aut Enthalten in Journal of nuclear materials Amsterdam [u.a.] : Elsevier Science, 1959 511, Seite 191-199 Online-Ressource (DE-627)320410730 (DE-600)2001279-2 (DE-576)251938174 nnns volume:511 pages:191-199 GBV_USEFLAG_U SYSFLAG_U GBV_ELV 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_63 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_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_224 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2336 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4313 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4393 51.40 Werkstoffe für bestimmte Anwendungsgebiete 52.55 Kerntechnik Reaktortechnik 33.81 Kernfusion 33.80 Plasmaphysik AR 511 191-199
allfieldsGer	10.1016/j.jnucmat.2018.09.016 doi (DE-627)ELV000952109 (ELSEVIER)S0022-3115(18)30794-3 DE-627 ger DE-627 rda eng 530 620 DE-600 51.40 bkl 52.55 bkl 33.81 bkl 33.80 bkl Zhao, Dandan verfasserin aut Investigation of ion irradiation hardening behaviors of tempered and long-term thermal aged T92 steel 2018 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier 9Cr ferritic/martensitic steels are promising materials for in-core components in advanced Gen-IV reactors. In these applications, their long-term microstructural stability under thermal exposure and resistance to neutron irradiation are essential. Tempered (unaged) and long-term thermal aged T92 samples were used to evaluate the effects of thermal aging and ion irradiation on the microstructure and micromechanical properties of the steel. Both the tempered and aged samples were irradiated with 3 MeV Fe11+ ions to 0.25, 0.50, 1.00 and 5.00 dpa at room temperature. Using the nanoindentation technique, the irradiation hardening behaviors of T92 steel were investigated. The irradiation hardening effect was observed in both the tempered and aged T92 samples. To eliminate the soft substrate effect, the critical indentation depth was determined using the ratio of the average hardness of irradiated and unirradiated samples at the same depth. Under the same irradiation conditions, the macroscopic hardness values of the aged T92 samples after irradiation were lower than those of the tempered samples. The irradiation hardening effect was more significant in the aged T92 due to the decreased dislocation density and the coarsened martensitic lath after long-term thermal aging. Ferritic/martensitic steels Ion irradiation Thermal aging Irradiation hardening Li, Shilei verfasserin (orcid)0000-0001-5432-9475 aut Wang, Yanli verfasserin (orcid)0000-0003-1284-1547 aut Liu, Fang verfasserin (orcid)0000-0002-3468-4450 aut Wang, Xitao verfasserin (orcid)0000-0002-1138-3372 aut Enthalten in Journal of nuclear materials Amsterdam [u.a.] : Elsevier Science, 1959 511, Seite 191-199 Online-Ressource (DE-627)320410730 (DE-600)2001279-2 (DE-576)251938174 nnns volume:511 pages:191-199 GBV_USEFLAG_U SYSFLAG_U GBV_ELV 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_63 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_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_224 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2336 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4313 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4393 51.40 Werkstoffe für bestimmte Anwendungsgebiete 52.55 Kerntechnik Reaktortechnik 33.81 Kernfusion 33.80 Plasmaphysik AR 511 191-199
allfieldsSound	10.1016/j.jnucmat.2018.09.016 doi (DE-627)ELV000952109 (ELSEVIER)S0022-3115(18)30794-3 DE-627 ger DE-627 rda eng 530 620 DE-600 51.40 bkl 52.55 bkl 33.81 bkl 33.80 bkl Zhao, Dandan verfasserin aut Investigation of ion irradiation hardening behaviors of tempered and long-term thermal aged T92 steel 2018 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier 9Cr ferritic/martensitic steels are promising materials for in-core components in advanced Gen-IV reactors. In these applications, their long-term microstructural stability under thermal exposure and resistance to neutron irradiation are essential. Tempered (unaged) and long-term thermal aged T92 samples were used to evaluate the effects of thermal aging and ion irradiation on the microstructure and micromechanical properties of the steel. Both the tempered and aged samples were irradiated with 3 MeV Fe11+ ions to 0.25, 0.50, 1.00 and 5.00 dpa at room temperature. Using the nanoindentation technique, the irradiation hardening behaviors of T92 steel were investigated. The irradiation hardening effect was observed in both the tempered and aged T92 samples. To eliminate the soft substrate effect, the critical indentation depth was determined using the ratio of the average hardness of irradiated and unirradiated samples at the same depth. Under the same irradiation conditions, the macroscopic hardness values of the aged T92 samples after irradiation were lower than those of the tempered samples. The irradiation hardening effect was more significant in the aged T92 due to the decreased dislocation density and the coarsened martensitic lath after long-term thermal aging. Ferritic/martensitic steels Ion irradiation Thermal aging Irradiation hardening Li, Shilei verfasserin (orcid)0000-0001-5432-9475 aut Wang, Yanli verfasserin (orcid)0000-0003-1284-1547 aut Liu, Fang verfasserin (orcid)0000-0002-3468-4450 aut Wang, Xitao verfasserin (orcid)0000-0002-1138-3372 aut Enthalten in Journal of nuclear materials Amsterdam [u.a.] : Elsevier Science, 1959 511, Seite 191-199 Online-Ressource (DE-627)320410730 (DE-600)2001279-2 (DE-576)251938174 nnns volume:511 pages:191-199 GBV_USEFLAG_U SYSFLAG_U GBV_ELV 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_63 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_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_224 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2336 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4313 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4393 51.40 Werkstoffe für bestimmte Anwendungsgebiete 52.55 Kerntechnik Reaktortechnik 33.81 Kernfusion 33.80 Plasmaphysik AR 511 191-199
language	English
source	Enthalten in Journal of nuclear materials 511, Seite 191-199 volume:511 pages:191-199
sourceStr	Enthalten in Journal of nuclear materials 511, Seite 191-199 volume:511 pages:191-199
format_phy_str_mv	Article
bklname	Werkstoffe für bestimmte Anwendungsgebiete Kerntechnik Reaktortechnik Kernfusion Plasmaphysik
institution	findex.gbv.de
topic_facet	Ferritic/martensitic steels Ion irradiation Thermal aging Irradiation hardening
dewey-raw	530
isfreeaccess_bool	false
container_title	Journal of nuclear materials
authorswithroles_txt_mv	Zhao, Dandan @@aut@@ Li, Shilei @@aut@@ Wang, Yanli @@aut@@ Liu, Fang @@aut@@ Wang, Xitao @@aut@@
publishDateDaySort_date	2018-01-01T00:00:00Z
hierarchy_top_id	320410730
dewey-sort	3530
id	ELV000952109
language_de	englisch
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author	Zhao, Dandan
spellingShingle	Zhao, Dandan ddc 530 bkl 51.40 bkl 52.55 bkl 33.81 bkl 33.80 misc Ferritic/martensitic steels misc Ion irradiation misc Thermal aging misc Irradiation hardening Investigation of ion irradiation hardening behaviors of tempered and long-term thermal aged T92 steel
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topic_title	530 620 DE-600 51.40 bkl 52.55 bkl 33.81 bkl 33.80 bkl Investigation of ion irradiation hardening behaviors of tempered and long-term thermal aged T92 steel Ferritic/martensitic steels Ion irradiation Thermal aging Irradiation hardening
topic	ddc 530 bkl 51.40 bkl 52.55 bkl 33.81 bkl 33.80 misc Ferritic/martensitic steels misc Ion irradiation misc Thermal aging misc Irradiation hardening
topic_unstemmed	ddc 530 bkl 51.40 bkl 52.55 bkl 33.81 bkl 33.80 misc Ferritic/martensitic steels misc Ion irradiation misc Thermal aging misc Irradiation hardening
topic_browse	ddc 530 bkl 51.40 bkl 52.55 bkl 33.81 bkl 33.80 misc Ferritic/martensitic steels misc Ion irradiation misc Thermal aging misc Irradiation hardening
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title	Investigation of ion irradiation hardening behaviors of tempered and long-term thermal aged T92 steel
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title_full	Investigation of ion irradiation hardening behaviors of tempered and long-term thermal aged T92 steel
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author_browse	Zhao, Dandan Li, Shilei Wang, Yanli Liu, Fang Wang, Xitao
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title_sort	investigation of ion irradiation hardening behaviors of tempered and long-term thermal aged t92 steel
title_auth	Investigation of ion irradiation hardening behaviors of tempered and long-term thermal aged T92 steel
abstract	9Cr ferritic/martensitic steels are promising materials for in-core components in advanced Gen-IV reactors. In these applications, their long-term microstructural stability under thermal exposure and resistance to neutron irradiation are essential. Tempered (unaged) and long-term thermal aged T92 samples were used to evaluate the effects of thermal aging and ion irradiation on the microstructure and micromechanical properties of the steel. Both the tempered and aged samples were irradiated with 3 MeV Fe11+ ions to 0.25, 0.50, 1.00 and 5.00 dpa at room temperature. Using the nanoindentation technique, the irradiation hardening behaviors of T92 steel were investigated. The irradiation hardening effect was observed in both the tempered and aged T92 samples. To eliminate the soft substrate effect, the critical indentation depth was determined using the ratio of the average hardness of irradiated and unirradiated samples at the same depth. Under the same irradiation conditions, the macroscopic hardness values of the aged T92 samples after irradiation were lower than those of the tempered samples. The irradiation hardening effect was more significant in the aged T92 due to the decreased dislocation density and the coarsened martensitic lath after long-term thermal aging.
abstractGer	9Cr ferritic/martensitic steels are promising materials for in-core components in advanced Gen-IV reactors. In these applications, their long-term microstructural stability under thermal exposure and resistance to neutron irradiation are essential. Tempered (unaged) and long-term thermal aged T92 samples were used to evaluate the effects of thermal aging and ion irradiation on the microstructure and micromechanical properties of the steel. Both the tempered and aged samples were irradiated with 3 MeV Fe11+ ions to 0.25, 0.50, 1.00 and 5.00 dpa at room temperature. Using the nanoindentation technique, the irradiation hardening behaviors of T92 steel were investigated. The irradiation hardening effect was observed in both the tempered and aged T92 samples. To eliminate the soft substrate effect, the critical indentation depth was determined using the ratio of the average hardness of irradiated and unirradiated samples at the same depth. Under the same irradiation conditions, the macroscopic hardness values of the aged T92 samples after irradiation were lower than those of the tempered samples. The irradiation hardening effect was more significant in the aged T92 due to the decreased dislocation density and the coarsened martensitic lath after long-term thermal aging.
abstract_unstemmed	9Cr ferritic/martensitic steels are promising materials for in-core components in advanced Gen-IV reactors. In these applications, their long-term microstructural stability under thermal exposure and resistance to neutron irradiation are essential. Tempered (unaged) and long-term thermal aged T92 samples were used to evaluate the effects of thermal aging and ion irradiation on the microstructure and micromechanical properties of the steel. Both the tempered and aged samples were irradiated with 3 MeV Fe11+ ions to 0.25, 0.50, 1.00 and 5.00 dpa at room temperature. Using the nanoindentation technique, the irradiation hardening behaviors of T92 steel were investigated. The irradiation hardening effect was observed in both the tempered and aged T92 samples. To eliminate the soft substrate effect, the critical indentation depth was determined using the ratio of the average hardness of irradiated and unirradiated samples at the same depth. Under the same irradiation conditions, the macroscopic hardness values of the aged T92 samples after irradiation were lower than those of the tempered samples. The irradiation hardening effect was more significant in the aged T92 due to the decreased dislocation density and the coarsened martensitic lath after long-term thermal aging.
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title_short	Investigation of ion irradiation hardening behaviors of tempered and long-term thermal aged T92 steel
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author2	Li, Shilei Wang, Yanli Liu, Fang Wang, Xitao
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doi_str	10.1016/j.jnucmat.2018.09.016
up_date	2024-07-06T19:43:33.721Z
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Investigation of ion irradiation hardening behaviors of tempered and long-term thermal aged T92 steel

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