TY - JOUR
T1 - Effects of Thermal Annealing on the Macroscopic Dimension and Lattice Parameter of Heavily Neutron-Irradiated Silicon Carbide
AU - Miyazaki, Hiroyuki
AU - Suzuki, Tetsuya
AU - Yano, Toyohiko
AU - Iseki, Takayoshi
N1 - Funding Information:
The present study was supported in part by the program of Grant-in-Aids for Fusion and for Scientific Research of the Ministry of Education, Science and Culture, Japan. For many valuable suggestions and constructive discussion in conducting the present study, the authors express their deep gratitude to Mr. M. Ito and Mr. S. Onose of the Power Reactor and Nuclear Fuel Development Corp.
PY - 1992
Y1 - 1992
N2 - Reaction-sintered (β-SiC specimens were neutron-irradiated in fast breeder reactors to fluences from 3.0×1024 to 1.7×1027 n/m2 (E>0.1 MeV) at temperatures from 370 to 620°C. Irradiation to fluences above 4.8×1026 n/m2 caused swelling (growth) that was significantly greater in respect of macroscopic dimension than of lattice parameter. These highly irradiated specimens also showed significant broadening of their X-ray line profiles, accompanied by generation of interstitial dislocation loops. Upon annealing, all specimens, irrespectively of the fluence to which they had been irradiated, tended toward recovery of their swelled macroscopic dimension and lattice parameter. This tendency was initiated when the annealing temperature exceeded that of irradiation, with the percentage of residual swelling lowering roughly in proportion to annealing temperature. The more highly irradiated specimens, in which the macroscopic dimension had swelled significantly more than the lattice parameter, lowered their percentages of residual swelling while maintaining a constant difference between them, as the annealing temperature was raised from that of irradiation to 1,200°C. In a certain range of higher annealing temperatures, the lattice parameter fell below the pre-irradiation level. In the range below 1,200°C, the broadened X-ray line profile indicated no tendency to recover. Microstruc-tural observations have indicated that the size and the number density of dislocation loops remain unchanged up to 1,000°C. The recovery of swelled macroscopic dimension and lattice parameter by annealing is discussed in terms of the recombination of point defects, which occurs even in the specimens irradiated to 1.7×l027n/m2 fluence.
AB - Reaction-sintered (β-SiC specimens were neutron-irradiated in fast breeder reactors to fluences from 3.0×1024 to 1.7×1027 n/m2 (E>0.1 MeV) at temperatures from 370 to 620°C. Irradiation to fluences above 4.8×1026 n/m2 caused swelling (growth) that was significantly greater in respect of macroscopic dimension than of lattice parameter. These highly irradiated specimens also showed significant broadening of their X-ray line profiles, accompanied by generation of interstitial dislocation loops. Upon annealing, all specimens, irrespectively of the fluence to which they had been irradiated, tended toward recovery of their swelled macroscopic dimension and lattice parameter. This tendency was initiated when the annealing temperature exceeded that of irradiation, with the percentage of residual swelling lowering roughly in proportion to annealing temperature. The more highly irradiated specimens, in which the macroscopic dimension had swelled significantly more than the lattice parameter, lowered their percentages of residual swelling while maintaining a constant difference between them, as the annealing temperature was raised from that of irradiation to 1,200°C. In a certain range of higher annealing temperatures, the lattice parameter fell below the pre-irradiation level. In the range below 1,200°C, the broadened X-ray line profile indicated no tendency to recover. Microstruc-tural observations have indicated that the size and the number density of dislocation loops remain unchanged up to 1,000°C. The recovery of swelled macroscopic dimension and lattice parameter by annealing is discussed in terms of the recombination of point defects, which occurs even in the specimens irradiated to 1.7×l027n/m2 fluence.
KW - X-ray diffraction
KW - X-ray line broadening
KW - dislocation loop
KW - irradiation temperature
KW - lattice parameter
KW - macroscopic dimension
KW - neutron irradiation
KW - point defects
KW - radiation doses
KW - silicon carbide
KW - thermal annealing
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U2 - 10.3327/jnst.29.656
DO - 10.3327/jnst.29.656
M3 - Article
AN - SCOPUS:85004220097
SN - 0022-3131
VL - 29
SP - 656
EP - 663
JO - Journal of Nuclear Science and Technology
JF - Journal of Nuclear Science and Technology
IS - 7
ER -