RADIATION-INDUCED SEGREGATION IN IRRADIATED TYPE-304 STAINLESS-STEELS

被引:50
|
作者
KENIK, EA
机构
[1] Metals and Ceramics Division, Oak Ridge National Laboratory, Oak Ridge, TN 37831
关键词
D O I
10.1016/0022-3115(92)90503-D
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Grain boundary radiation-induced segregation (RIS) in two Type 304 stainless steels neutron-irradiated at 288-degrees-C has been investigated by analytical electron microscopy. In the conventional alloy (CP), narrow (less-than-or-equal-to 5 nm width) RIS zones depleted in chromium and iron and enriched in silicon, phosphorus, and nickel were observed near grain boundaries. For the higher purity alloy (HP), similar width (less-than-or-equal-to 6 nm) RIS zones depleted in chromium and enriched in nickel and iron were observed at boundaries, though at reduced magnitudes relative to those in the CP material. No significant segregation of silicon or phosphorus was observed in the HP material. RIS zones associated with faulted dislocation loops in the CP material were detected and shown to be depleted in chromium and enriched in nickel and iron relative to the matrix.
引用
收藏
页码:239 / 246
页数:8
相关论文
共 50 条
  • [41] Atomic scale investigation of radiation-induced segregation in austenitic stainless steels
    Etienne, A.
    Radiguet, B.
    Cunningham, N. J.
    Odette, G. R.
    Pareige, P.
    JOURNAL OF NUCLEAR MATERIALS, 2010, 406 (02) : 244 - 250
  • [42] Radiation-induced segregation in austenitic stainless steel type 304: Effect of high fraction of twin boundaries
    Ahmedabadi, Parag
    Kain, V.
    Arora, K.
    Samajdar, I.
    Sharma, S. C.
    Ravindra, S.
    Bhagwat, P.
    MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2011, 528 (25-26): : 7541 - 7551
  • [43] Radiation-induced segregation at grain boundaries in AL-6XN stainless steels irradiated by hydrogen ions
    Long, Yunxiang
    Zheng, Zhongcheng
    Guo, Liping
    Zhang, Weiping
    Shen, Zhenyu
    Tang, Rui
    RADIATION PHYSICS AND CHEMISTRY, 2018, 145 : 116 - 121
  • [44] Post-irradiation annealing of dislocation microstructure and radiation-induced segregation in proton-irradiated stainless steels
    Busby, JT
    Was, GS
    Kenik, EA
    MICROSTRUCTURAL PROCESSES IN IRRADIATED MATERIALS, 1999, 540 : 495 - 500
  • [45] THE DEFORMATION-BEHAVIOR OF TYPE-304, TYPE-316, AND TYPE-317 AUSTENITIC STAINLESS-STEELS DURING HOT TORSION
    RYAN, ND
    MCQUEEN, HJ
    JONAS, JJ
    CANADIAN METALLURGICAL QUARTERLY, 1983, 22 (03) : 369 - 378
  • [46] RELATIONSHIP BETWEEN CREEP-RUPTURE ELONGATION AND TIME-TO-RUPTURE IN TYPE-304 AND TYPE-316 STAINLESS-STEELS
    NAKAZAWA, T
    ABO, H
    KOMATSU, H
    TANINO, M
    TETSU TO HAGANE-JOURNAL OF THE IRON AND STEEL INSTITUTE OF JAPAN, 1989, 75 (12): : 2234 - 2241
  • [47] Numerical simulation modeling on the effects of grain boundary misorientation on radiation-induced solute segregation in 304 austenitic stainless steels
    Duh, TS
    Kai, JJ
    Chen, FR
    Wang, LH
    JOURNAL OF NUCLEAR MATERIALS, 2001, 294 (03) : 267 - 273
  • [48] FAST-NEUTRON SWELLING OF TYPE 304 STAINLESS-STEELS
    FLINN, JE
    WEINER, RA
    HOFMAN, GL
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1978, 28 (JUN): : 224 - 225
  • [49] Effect of process variables on the crevice corrosion in type-304 stainless steels
    Adeniyi A.G.
    Ighalo J.O.
    Recent Innovations in Chemical Engineering, 2020, 13 (05) : 379 - 389
  • [50] FATIGUE PROPERTIES OF HIGHLY IRRADIATED TYPE-304 STAINLESS-STEEL
    SMITH, HH
    WATSON, HE
    SHAHINIA.P
    REPORT OF NRL PROGRESS, 1973, (JAN): : 30 - 31