2007
DOI: 10.1016/j.jnucmat.2007.03.145
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Microstructural development of a heavily neutron-irradiated ODS ferritic steel (MA957) at elevated temperature

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Cited by 76 publications
(26 citation statements)
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“…Oxide dispersion strengthened (ODS) ferritic steels show good creep strength [1] and neutron irradiation tolerance [2]. Therefore, these materials are considered for cladding tube application in fast reactors.…”
Section: Introductionmentioning
confidence: 99%
“…Oxide dispersion strengthened (ODS) ferritic steels show good creep strength [1] and neutron irradiation tolerance [2]. Therefore, these materials are considered for cladding tube application in fast reactors.…”
Section: Introductionmentioning
confidence: 99%
“…This is due to their excellent creep properties [1][2][3][4][5][6][7][8][9] and superior irradiation resistance [7,[10][11][12][13][14][15][16][17][18], compared to other conventional heat resistant steels such as 9Cr ferritic/martensitic steels and austenitic steels. These very attractive properties are obtained by means of nanometric oxide particles dispersed in the matrix.…”
Section: Introductionmentioning
confidence: 99%
“…ODS alloys are attractive structural materials for advanced fission and fusion reactors, because of their highly improved creep properties [1][2][3][4][5][6][7][8] and good irradiation resistance [3,[9][10][11][12][13][14][15][16] compared to conventional ferritic/martensitic and austenitic steels. Such superior properties are obtained through nanosized oxide particles dispersed in the matrix.…”
Section: Introductionmentioning
confidence: 99%