TY - JOUR
T1 - Irradiation hardening and microstructaral evolution in Fe-Cu model aloys
AU - Kitao, Takeshi
AU - Kasada, Ryuta
AU - Kimura, Akihiko
AU - Nakata, Hayato
AU - Fukuya, Kouji
AU - Matsui, Hideki
AU - Narui, Minoru
PY - 2004/1/1
Y1 - 2004/1/1
N2 - Irradiation hardening and microstructural evolution under neutron and electron irradiation have been investigated for pure-Fe and Fe-Cu model alloys. Neutron and electron irradiations were performed in the Japan Material Test Reactor (JMTR) and with using Phodtron electron accelerator at about 290°C and 270±30°C, respectively. Irradiation hardening of pure-Fe and Fe-Cu model alloys is saturated at about 1 × 10-3 dpa in both the neutron and electron irradiation. Irradiation hardening recovered in two temperature ranges. The recovery in the lower temperature range depends on copper concentration and electron irradiation dose, while the recovery at a higher temperature range does not. Recovery behavior of the irradiation hardening suggests indirectly that copper atoms suppress the growth of interstitial clusters. The recovery behavior of positron lifetime does not coincide with that of the hardness, suggesting that the vacancy clusters are not the direct main factor controlling the hardening by matrix damages. irradiation hardening, matrix defect, copper-rich.
AB - Irradiation hardening and microstructural evolution under neutron and electron irradiation have been investigated for pure-Fe and Fe-Cu model alloys. Neutron and electron irradiations were performed in the Japan Material Test Reactor (JMTR) and with using Phodtron electron accelerator at about 290°C and 270±30°C, respectively. Irradiation hardening of pure-Fe and Fe-Cu model alloys is saturated at about 1 × 10-3 dpa in both the neutron and electron irradiation. Irradiation hardening recovered in two temperature ranges. The recovery in the lower temperature range depends on copper concentration and electron irradiation dose, while the recovery at a higher temperature range does not. Recovery behavior of the irradiation hardening suggests indirectly that copper atoms suppress the growth of interstitial clusters. The recovery behavior of positron lifetime does not coincide with that of the hardness, suggesting that the vacancy clusters are not the direct main factor controlling the hardening by matrix damages. irradiation hardening, matrix defect, copper-rich.
KW - Electron irradiation
KW - Fe-Cu model alloys
KW - Neutron irradiation
KW - Post-irradiation annealing
KW - Precipitate
KW - Vacancy cluster
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M3 - Conference article
AN - SCOPUS:32944466424
SP - 365
EP - 375
JO - ASTM Special Technical Publication
JF - ASTM Special Technical Publication
SN - 1040-3094
IS - 1447
T2 - Effects of Radiation on Materials: 21st International Symposium
Y2 - 18 June 2002 through 20 June 2002
ER -