TY - JOUR
T1 - Effects of precipitation morphology on toughness of reduced activation ferritic/martensitic steels
AU - Sakasegawa, H.
AU - Hirose, T.
AU - Kohyama, A.
AU - Katoh, Y.
AU - Harada, T.
AU - Asakura, K.
AU - Kumagai, T.
PY - 2002/12
Y1 - 2002/12
N2 - Reduced activation ferritic/martensitic steels (RAFs) are leading candidates for structural materials of D-T fusion reactors. It is reported that 9Cr-2W-V, Ta steel (JLF-1), one of the RAFs, has superior phase stability, swelling resistance and mechanical properties against high-fluence neutron irradiation. Recently 9Cr-xW-V, Ta steels (x = 2.5, 3.0 and 3.5, JLS-series hereafter) were developed for use at higher temperatures. In this work, JLF-1 and JLS-series were thermal-aged at 823 and 923 K. Charpy impact tests were performed before and after thermal-aging. Microstructural features were observed using transmission electron microscope with energy dispersive X-ray spectrometer. From the results of Charpy impact tests, the ductile to brittle transition temperature was found to increase both by thermal-aging and by increasing tungsten content. This behavior was consistent with microstructural evolution of intergranular precipitates such as M23C6 and Laves phase coarsening.
AB - Reduced activation ferritic/martensitic steels (RAFs) are leading candidates for structural materials of D-T fusion reactors. It is reported that 9Cr-2W-V, Ta steel (JLF-1), one of the RAFs, has superior phase stability, swelling resistance and mechanical properties against high-fluence neutron irradiation. Recently 9Cr-xW-V, Ta steels (x = 2.5, 3.0 and 3.5, JLS-series hereafter) were developed for use at higher temperatures. In this work, JLF-1 and JLS-series were thermal-aged at 823 and 923 K. Charpy impact tests were performed before and after thermal-aging. Microstructural features were observed using transmission electron microscope with energy dispersive X-ray spectrometer. From the results of Charpy impact tests, the ductile to brittle transition temperature was found to increase both by thermal-aging and by increasing tungsten content. This behavior was consistent with microstructural evolution of intergranular precipitates such as M23C6 and Laves phase coarsening.
UR - http://www.scopus.com/inward/record.url?scp=0036938942&partnerID=8YFLogxK
U2 - 10.1016/S0022-3115(02)01083-8
DO - 10.1016/S0022-3115(02)01083-8
M3 - Article
AN - SCOPUS:0036938942
SN - 0022-3115
VL - 307-311
SP - 490
EP - 494
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
IS - 1 SUPPL.
ER -
