THE EFFECT OF SOLUTE CONTENT ON GRAIN-BOUNDARY SEGREGATION IN ELECTRON-IRRADIATED FE-CR-MN ALLOYS

被引:19
作者
KATO, T [1 ]
TAKAHASHI, H [1 ]
OHNUKI, S [1 ]
NAKATA, K [1 ]
KUNIYA, J [1 ]
机构
[1] HOKKAIDO UNIV,FAC ENGN,SAPPORO,HOKKAIDO 060,JAPAN
关键词
D O I
10.1016/0022-3115(91)90165-4
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Solute distribution and microstructural development in the vicinity of grain boundaries in ferritic Fe-10Cr-xMn-3Al (x = 5, 10 or 15) alloys were studied during electron irradiation to 10 dpa at 723 K. In addition, X-ray diffraction analysis was performed for determination of the volume size factor of solutes. The oversized solute atoms, manganese and aluminum, were depleted at grain boundaries, whereas the concentration of the oversized chromium rose sharply at the boundary. The amount of segregation of the solutes decreased with increasing atomic volume depending on manganese content. Segregation of aluminum, which had the greater volume size factor relative to that of manganese, was higher than that of manganese. The amount of radiation-induced segregation of manganese and aluminum at the grain boundary is consistent with arguments based on the atomic size effect, but the enrichment of chromium at the grain boundary is not and seems to related primarily to the formation of chromium-rich precipitates at the boundary.
引用
收藏
页码:623 / 625
页数:3
相关论文
共 10 条
[1]   DEVELOPMENT OF REDUCED ACTIVATION ALLOYS FOR FUSION SERVICE [J].
BRAGER, HR ;
GARNER, FA ;
GELLES, DS ;
HAMILTON, ML .
JOURNAL OF NUCLEAR MATERIALS, 1985, 133 (AUG) :907-911
[2]  
Garner F. A., 1987, ASTM STP, V955, P195
[3]   Quantitative Size-Factors for Metallic Solid Solutions [J].
King, H. W. .
JOURNAL OF MATERIALS SCIENCE, 1966, 1 (01) :79-90
[4]   SOLUTE SEGREGATION ALONG NON-MIGRATED AND MIGRATED GRAIN-BOUNDARIES DURING ELECTRON-IRRADIATION IN AUSTENITIC STAINLESS-STEELS [J].
NAKATA, K ;
MASAOKA, I .
JOURNAL OF NUCLEAR MATERIALS, 1987, 150 (02) :186-193
[5]  
Ohnuki S., 1981, J NUCL MATER, V103-104, P1121
[6]   SEGREGATION OF ALLOYING ELEMENTS TO FREE SURFACES DURING IRRADIATION [J].
OKAMOTO, PR ;
WIEDERSICH, H .
JOURNAL OF NUCLEAR MATERIALS, 1974, 53 (01) :336-345
[7]   DAMAGE STRUCTURAL BEHAVIOR BY ELECTRON-IRRADIATION OF MN-CR AUSTENITIC STAINLESS-STEELS [J].
TAKAHASHI, H ;
TAKEYAMA, T ;
TANIKAWA, K ;
MIURA, R .
JOURNAL OF NUCLEAR MATERIALS, 1985, 133 (AUG) :566-570
[8]  
TAKAHASHI H, 1981, J NUCL MATER, V103, P1415
[9]  
TANAKA K, 1985, T IRON STEEL I JPN, V25, pB190
[10]  
1986, J NUCL MATER, V141, P1131