Effect of Test Temperature on Mechanical Properties of Austenitic 0.12C18Cr10NiTi and 0.08C16Cr11Ni3Mo Steels Irradiated by Fast Neutrons in the BN-350 Reactor
C18Cr10NiТi and 0.08C16Cr11Ni3Мo austenitic steels serve as structural materials for fuel assembly covers in the BN-350 fast reactor, as well as for the covers of transport packagings for transportation and storage of spent nuclear fuel (SNF). To predict failure of these elements, it is of paramount...
Ausführliche Beschreibung
Gespeichert in:
| Autor*in: |
Alexey Dikov [verfasserIn] |
|---|
| Format: |
Artikel |
|---|---|
| Sprache: |
Englisch |
| Erschienen: |
2017 |
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| Schlagwörter: |
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| Übergeordnetes Werk: |
Enthalten in: Diffusion and defect data / A - Baech : Trans Tech Publications Ltd, 1988, 375(2017), Seite 134 |
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| Übergeordnetes Werk: |
volume:375 ; year:2017 ; pages:134 |
| Links: |
|---|
| DOI / URN: |
10.4028/www.scientific.net/DDF.375.134 |
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| 245 | 1 | 0 | |a Effect of Test Temperature on Mechanical Properties of Austenitic 0.12C18Cr10NiTi and 0.08C16Cr11Ni3Mo Steels Irradiated by Fast Neutrons in the BN-350 Reactor |
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| 520 | |a C18Cr10NiТi and 0.08C16Cr11Ni3Мo austenitic steels serve as structural materials for fuel assembly covers in the BN-350 fast reactor, as well as for the covers of transport packagings for transportation and storage of spent nuclear fuel (SNF). To predict failure of these elements, it is of paramount importance to know their mechanical properties at elevated temperatures after in-pile irradiation. We performed tensile and creep tests at room temperature (RT), 350 °C and 450 °C of irradiated samples cut from the higher half of fuel duct pipes of the BN-350 reactor. A non-monotonic temperature dependence of tensile strength, yield stress, and relative elongation was shown. Microstructural investigation revealed the origin of this dependence lies in the different distribution of carbides and is also associated with the formation of α'-phase. | ||
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10.4028/www.scientific.net/DDF.375.134 doi PQ20170901 (DE-627)OLC1995108774 (DE-599)GBVOLC1995108774 (PRQ)p645-d41984f60277231a6a673526e9d4a8ffea4482d1383a4926c95c67880a14457b0 (KEY)0174552220170000375000000134effectoftesttemperatureonmechanicalpropertiesofaus DE-627 ger DE-627 rakwb eng 670 DE-600 Alexey Dikov verfasserin aut Effect of Test Temperature on Mechanical Properties of Austenitic 0.12C18Cr10NiTi and 0.08C16Cr11Ni3Mo Steels Irradiated by Fast Neutrons in the BN-350 Reactor 2017 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier C18Cr10NiТi and 0.08C16Cr11Ni3Мo austenitic steels serve as structural materials for fuel assembly covers in the BN-350 fast reactor, as well as for the covers of transport packagings for transportation and storage of spent nuclear fuel (SNF). To predict failure of these elements, it is of paramount importance to know their mechanical properties at elevated temperatures after in-pile irradiation. We performed tensile and creep tests at room temperature (RT), 350 °C and 450 °C of irradiated samples cut from the higher half of fuel duct pipes of the BN-350 reactor. A non-monotonic temperature dependence of tensile strength, yield stress, and relative elongation was shown. Microstructural investigation revealed the origin of this dependence lies in the different distribution of carbides and is also associated with the formation of α'-phase. Temperature Alloys Temperature dependence Mechanical properties Sergey Kislitsin oth Ivan Chernov oth Enthalten in Diffusion and defect data / A Baech : Trans Tech Publications Ltd, 1988 375(2017), Seite 134 (DE-627)130430897 (DE-600)636038-5 (DE-576)016840585 0377-6883 volume:375 year:2017 pages:134 http://dx.doi.org/10.4028/www.scientific.net/DDF.375.134 Volltext https://search.proquest.com/docview/1902543175 GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY AR 375 2017 134 |
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10.4028/www.scientific.net/DDF.375.134 doi PQ20170901 (DE-627)OLC1995108774 (DE-599)GBVOLC1995108774 (PRQ)p645-d41984f60277231a6a673526e9d4a8ffea4482d1383a4926c95c67880a14457b0 (KEY)0174552220170000375000000134effectoftesttemperatureonmechanicalpropertiesofaus DE-627 ger DE-627 rakwb eng 670 DE-600 Alexey Dikov verfasserin aut Effect of Test Temperature on Mechanical Properties of Austenitic 0.12C18Cr10NiTi and 0.08C16Cr11Ni3Mo Steels Irradiated by Fast Neutrons in the BN-350 Reactor 2017 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier C18Cr10NiТi and 0.08C16Cr11Ni3Мo austenitic steels serve as structural materials for fuel assembly covers in the BN-350 fast reactor, as well as for the covers of transport packagings for transportation and storage of spent nuclear fuel (SNF). To predict failure of these elements, it is of paramount importance to know their mechanical properties at elevated temperatures after in-pile irradiation. We performed tensile and creep tests at room temperature (RT), 350 °C and 450 °C of irradiated samples cut from the higher half of fuel duct pipes of the BN-350 reactor. A non-monotonic temperature dependence of tensile strength, yield stress, and relative elongation was shown. Microstructural investigation revealed the origin of this dependence lies in the different distribution of carbides and is also associated with the formation of α'-phase. Temperature Alloys Temperature dependence Mechanical properties Sergey Kislitsin oth Ivan Chernov oth Enthalten in Diffusion and defect data / A Baech : Trans Tech Publications Ltd, 1988 375(2017), Seite 134 (DE-627)130430897 (DE-600)636038-5 (DE-576)016840585 0377-6883 volume:375 year:2017 pages:134 http://dx.doi.org/10.4028/www.scientific.net/DDF.375.134 Volltext https://search.proquest.com/docview/1902543175 GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY AR 375 2017 134 |
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10.4028/www.scientific.net/DDF.375.134 doi PQ20170901 (DE-627)OLC1995108774 (DE-599)GBVOLC1995108774 (PRQ)p645-d41984f60277231a6a673526e9d4a8ffea4482d1383a4926c95c67880a14457b0 (KEY)0174552220170000375000000134effectoftesttemperatureonmechanicalpropertiesofaus DE-627 ger DE-627 rakwb eng 670 DE-600 Alexey Dikov verfasserin aut Effect of Test Temperature on Mechanical Properties of Austenitic 0.12C18Cr10NiTi and 0.08C16Cr11Ni3Mo Steels Irradiated by Fast Neutrons in the BN-350 Reactor 2017 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier C18Cr10NiТi and 0.08C16Cr11Ni3Мo austenitic steels serve as structural materials for fuel assembly covers in the BN-350 fast reactor, as well as for the covers of transport packagings for transportation and storage of spent nuclear fuel (SNF). To predict failure of these elements, it is of paramount importance to know their mechanical properties at elevated temperatures after in-pile irradiation. We performed tensile and creep tests at room temperature (RT), 350 °C and 450 °C of irradiated samples cut from the higher half of fuel duct pipes of the BN-350 reactor. A non-monotonic temperature dependence of tensile strength, yield stress, and relative elongation was shown. Microstructural investigation revealed the origin of this dependence lies in the different distribution of carbides and is also associated with the formation of α'-phase. Temperature Alloys Temperature dependence Mechanical properties Sergey Kislitsin oth Ivan Chernov oth Enthalten in Diffusion and defect data / A Baech : Trans Tech Publications Ltd, 1988 375(2017), Seite 134 (DE-627)130430897 (DE-600)636038-5 (DE-576)016840585 0377-6883 volume:375 year:2017 pages:134 http://dx.doi.org/10.4028/www.scientific.net/DDF.375.134 Volltext https://search.proquest.com/docview/1902543175 GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY AR 375 2017 134 |
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10.4028/www.scientific.net/DDF.375.134 doi PQ20170901 (DE-627)OLC1995108774 (DE-599)GBVOLC1995108774 (PRQ)p645-d41984f60277231a6a673526e9d4a8ffea4482d1383a4926c95c67880a14457b0 (KEY)0174552220170000375000000134effectoftesttemperatureonmechanicalpropertiesofaus DE-627 ger DE-627 rakwb eng 670 DE-600 Alexey Dikov verfasserin aut Effect of Test Temperature on Mechanical Properties of Austenitic 0.12C18Cr10NiTi and 0.08C16Cr11Ni3Mo Steels Irradiated by Fast Neutrons in the BN-350 Reactor 2017 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier C18Cr10NiТi and 0.08C16Cr11Ni3Мo austenitic steels serve as structural materials for fuel assembly covers in the BN-350 fast reactor, as well as for the covers of transport packagings for transportation and storage of spent nuclear fuel (SNF). To predict failure of these elements, it is of paramount importance to know their mechanical properties at elevated temperatures after in-pile irradiation. We performed tensile and creep tests at room temperature (RT), 350 °C and 450 °C of irradiated samples cut from the higher half of fuel duct pipes of the BN-350 reactor. A non-monotonic temperature dependence of tensile strength, yield stress, and relative elongation was shown. Microstructural investigation revealed the origin of this dependence lies in the different distribution of carbides and is also associated with the formation of α'-phase. Temperature Alloys Temperature dependence Mechanical properties Sergey Kislitsin oth Ivan Chernov oth Enthalten in Diffusion and defect data / A Baech : Trans Tech Publications Ltd, 1988 375(2017), Seite 134 (DE-627)130430897 (DE-600)636038-5 (DE-576)016840585 0377-6883 volume:375 year:2017 pages:134 http://dx.doi.org/10.4028/www.scientific.net/DDF.375.134 Volltext https://search.proquest.com/docview/1902543175 GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY AR 375 2017 134 |
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10.4028/www.scientific.net/DDF.375.134 doi PQ20170901 (DE-627)OLC1995108774 (DE-599)GBVOLC1995108774 (PRQ)p645-d41984f60277231a6a673526e9d4a8ffea4482d1383a4926c95c67880a14457b0 (KEY)0174552220170000375000000134effectoftesttemperatureonmechanicalpropertiesofaus DE-627 ger DE-627 rakwb eng 670 DE-600 Alexey Dikov verfasserin aut Effect of Test Temperature on Mechanical Properties of Austenitic 0.12C18Cr10NiTi and 0.08C16Cr11Ni3Mo Steels Irradiated by Fast Neutrons in the BN-350 Reactor 2017 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier C18Cr10NiТi and 0.08C16Cr11Ni3Мo austenitic steels serve as structural materials for fuel assembly covers in the BN-350 fast reactor, as well as for the covers of transport packagings for transportation and storage of spent nuclear fuel (SNF). To predict failure of these elements, it is of paramount importance to know their mechanical properties at elevated temperatures after in-pile irradiation. We performed tensile and creep tests at room temperature (RT), 350 °C and 450 °C of irradiated samples cut from the higher half of fuel duct pipes of the BN-350 reactor. A non-monotonic temperature dependence of tensile strength, yield stress, and relative elongation was shown. Microstructural investigation revealed the origin of this dependence lies in the different distribution of carbides and is also associated with the formation of α'-phase. Temperature Alloys Temperature dependence Mechanical properties Sergey Kislitsin oth Ivan Chernov oth Enthalten in Diffusion and defect data / A Baech : Trans Tech Publications Ltd, 1988 375(2017), Seite 134 (DE-627)130430897 (DE-600)636038-5 (DE-576)016840585 0377-6883 volume:375 year:2017 pages:134 http://dx.doi.org/10.4028/www.scientific.net/DDF.375.134 Volltext https://search.proquest.com/docview/1902543175 GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY AR 375 2017 134 |
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effect of test temperature on mechanical properties of austenitic 0.12c18cr10niti and 0.08c16cr11ni3mo steels irradiated by fast neutrons in the bn-350 reactor |
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Effect of Test Temperature on Mechanical Properties of Austenitic 0.12C18Cr10NiTi and 0.08C16Cr11Ni3Mo Steels Irradiated by Fast Neutrons in the BN-350 Reactor |
| abstract |
C18Cr10NiТi and 0.08C16Cr11Ni3Мo austenitic steels serve as structural materials for fuel assembly covers in the BN-350 fast reactor, as well as for the covers of transport packagings for transportation and storage of spent nuclear fuel (SNF). To predict failure of these elements, it is of paramount importance to know their mechanical properties at elevated temperatures after in-pile irradiation. We performed tensile and creep tests at room temperature (RT), 350 °C and 450 °C of irradiated samples cut from the higher half of fuel duct pipes of the BN-350 reactor. A non-monotonic temperature dependence of tensile strength, yield stress, and relative elongation was shown. Microstructural investigation revealed the origin of this dependence lies in the different distribution of carbides and is also associated with the formation of α'-phase. |
| abstractGer |
C18Cr10NiТi and 0.08C16Cr11Ni3Мo austenitic steels serve as structural materials for fuel assembly covers in the BN-350 fast reactor, as well as for the covers of transport packagings for transportation and storage of spent nuclear fuel (SNF). To predict failure of these elements, it is of paramount importance to know their mechanical properties at elevated temperatures after in-pile irradiation. We performed tensile and creep tests at room temperature (RT), 350 °C and 450 °C of irradiated samples cut from the higher half of fuel duct pipes of the BN-350 reactor. A non-monotonic temperature dependence of tensile strength, yield stress, and relative elongation was shown. Microstructural investigation revealed the origin of this dependence lies in the different distribution of carbides and is also associated with the formation of α'-phase. |
| abstract_unstemmed |
C18Cr10NiТi and 0.08C16Cr11Ni3Мo austenitic steels serve as structural materials for fuel assembly covers in the BN-350 fast reactor, as well as for the covers of transport packagings for transportation and storage of spent nuclear fuel (SNF). To predict failure of these elements, it is of paramount importance to know their mechanical properties at elevated temperatures after in-pile irradiation. We performed tensile and creep tests at room temperature (RT), 350 °C and 450 °C of irradiated samples cut from the higher half of fuel duct pipes of the BN-350 reactor. A non-monotonic temperature dependence of tensile strength, yield stress, and relative elongation was shown. Microstructural investigation revealed the origin of this dependence lies in the different distribution of carbides and is also associated with the formation of α'-phase. |
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| title_short |
Effect of Test Temperature on Mechanical Properties of Austenitic 0.12C18Cr10NiTi and 0.08C16Cr11Ni3Mo Steels Irradiated by Fast Neutrons in the BN-350 Reactor |
| url |
http://dx.doi.org/10.4028/www.scientific.net/DDF.375.134 https://search.proquest.com/docview/1902543175 |
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Sergey Kislitsin Ivan Chernov |
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10.4028/www.scientific.net/DDF.375.134 |
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2024-07-03T20:30:02.487Z |
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