TY - JOUR
T1 - Mechanical tests on two batches of oxide dispersion strengthened RAFM steel (EUROFER97)
AU - Lucon, Enrico
PY - 2003
Y1 - 2003
N2 - EUROFER97 is a 9CrWVTa reduced-activation ferritic/martensitic (RAFM) steel, modelled after the conventional
T91 alloy (9Cr/1Mo/0.2V/0.08Nb); some of the elements in T91 that will transmute in a fusion neutron spectrum into
high-energy radiation emitters with long-half life have been selectively replaced by other elements (W has replaced Mo
and Ta has replaced Nb). Such replacements do not influence the mechanical properties but are beneficial from a
reduced-activation point of view. The latest developments in the ferritic/martensitic steels for nuclear applications tend
toward a fine microstructure with small prior austenite grains and a low number of inclusions, in order to achieve an
optimal combination of toughness, strength and high-temperature properties. On the other hand, higher operating
temperatures may translate into a better efficiency of power reactors; oxide dispersion strengthening (ODS) offers the
potential of increasing the operating temperature of RAFM steels from 550 °C to about 625 °C, while retaining
satisfactory mechanical properties. A mechanical characterisation of two ODS versions of EUROFER97 has been
carried out at SCK-CEN by means of tensile and instrumented KLST Charpy tests. The two alloys, which contain
different weight percentages of Y2O3 (0.3 and 0.5%), have been characterised in two orientations in the ‘as-HIPped’
state, that is without any post-HIPping heat treatment.
AB - EUROFER97 is a 9CrWVTa reduced-activation ferritic/martensitic (RAFM) steel, modelled after the conventional
T91 alloy (9Cr/1Mo/0.2V/0.08Nb); some of the elements in T91 that will transmute in a fusion neutron spectrum into
high-energy radiation emitters with long-half life have been selectively replaced by other elements (W has replaced Mo
and Ta has replaced Nb). Such replacements do not influence the mechanical properties but are beneficial from a
reduced-activation point of view. The latest developments in the ferritic/martensitic steels for nuclear applications tend
toward a fine microstructure with small prior austenite grains and a low number of inclusions, in order to achieve an
optimal combination of toughness, strength and high-temperature properties. On the other hand, higher operating
temperatures may translate into a better efficiency of power reactors; oxide dispersion strengthening (ODS) offers the
potential of increasing the operating temperature of RAFM steels from 550 °C to about 625 °C, while retaining
satisfactory mechanical properties. A mechanical characterisation of two ODS versions of EUROFER97 has been
carried out at SCK-CEN by means of tensile and instrumented KLST Charpy tests. The two alloys, which contain
different weight percentages of Y2O3 (0.3 and 0.5%), have been characterised in two orientations in the ‘as-HIPped’
state, that is without any post-HIPping heat treatment.
KW - RAFM steel
KW - EUROFER97
KW - Oxide dispersion strengthening
KW - Hot isostatic pressing
KW - KLST charpy specimens
U2 - 10.1016/S0920-3796(02)00098-4
DO - 10.1016/S0920-3796(02)00098-4
M3 - Article
SN - 0920-3796
VL - 61-62
SP - 683
EP - 689
JO - fusion engineering and design
JF - fusion engineering and design
ER -