TY - GEN
T1 - Effects of neutron dose, dose rate, and irradiation temperature on the irradiation embrittlement of a low-copper reactor pressure vessel steel
AU - Kasada, Ryuta
AU - Kudo, Takeshi
AU - Kimura, Akihiko
AU - Matsui, Hideki
AU - Narui, Minoru
PY - 2006
Y1 - 2006
N2 - A series of irradiation experiments to investigate the effects of neutron tluence and flux on reactor pressure vessel (RPV) steels has been performed using the Japan Material Testing Reactor (JMTR). The irradiation temperature has been precisely controlled at 290°C within an error of ±2°C during reactor operation. The neutron fluence and tlux ranged from 9.3 × 1017 to 1.1 × 1020 n/cm2 and from 1.4 × 1011 to 6.3 × 1013 n/cm2/s, respectively. The material used in the present study was an A533B RPV steel in which the copper and phosphorous concentrations are 0.03 and 0.002 wt%, respectively. Charpy impact test results with one-third sized specimens showed no dose-rate dependence. Microstructural observation revealed that a higher irradiation temperature at around 340°C resulted in formation of rather large dislocation loops and smaller microvoids.
AB - A series of irradiation experiments to investigate the effects of neutron tluence and flux on reactor pressure vessel (RPV) steels has been performed using the Japan Material Testing Reactor (JMTR). The irradiation temperature has been precisely controlled at 290°C within an error of ±2°C during reactor operation. The neutron fluence and tlux ranged from 9.3 × 1017 to 1.1 × 1020 n/cm2 and from 1.4 × 1011 to 6.3 × 1013 n/cm2/s, respectively. The material used in the present study was an A533B RPV steel in which the copper and phosphorous concentrations are 0.03 and 0.002 wt%, respectively. Charpy impact test results with one-third sized specimens showed no dose-rate dependence. Microstructural observation revealed that a higher irradiation temperature at around 340°C resulted in formation of rather large dislocation loops and smaller microvoids.
KW - Charpy impact test
KW - Dose rate effects
KW - Irradiation embrittlement
KW - Irradiation hardening
KW - Reactor pressure vessel steel
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M3 - Conference contribution
AN - SCOPUS:70249128357
SN - 0803134010
SN - 9780803134010
T3 - ASTM Special Technical Publication
SP - 225
EP - 235
BT - Effects of Radiation on Materials
PB - American Society for Testing and Materials
T2 - 22nd Symposium on Effects of Radiation on Materials
Y2 - 8 June 2004 through 10 June 2004
ER -