CORROSION MODELS FOR PERFORMANCE ASSESSMENT OF HIGH-LEVEL RADIOACTIVE-WASTE CONTAINERS

被引:11
作者
FARMER, JC
GDOWSKI, GE
MCCRIGHT, RD
AHLUWAHLIA, HS
机构
[1] KMI ENERGY,LIVERMORE,CA
[2] SCI & ENGN ASSOCIATES INC,LIVERMORE,CA
关键词
D O I
10.1016/0029-5493(91)90329-G
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The present plan for disposal of high-level radioactive waste in the USA is to seal the waste in containers before emplacement in a geologic repository. A proposed site at Yucca Mountain, Nevada, is presently being evaluated for its suitability as a geologic repository. The containers will probably be made of either an austenitic or a copper-based alloy. Models of alloy degradation are being used to predict the long-term performance of the containers under repository conditions. The models are of uniform oxidation and corrosion, localized corrosion, and stress corrosion cracking, and are applicable to worst-case scenarios of container degradation. This paper reviews several of the models.
引用
收藏
页码:57 / 88
页数:32
相关论文
共 128 条
  • [1] AALTONEN P, 1984, YJT8421 NUCL WAST CO
  • [2] AALTONEN P, 1985, PREDICTIVE CAPABILIT, P329
  • [3] ANDRESEN PL, 1987, 3RD INT C DEGR MAT N
  • [4] ANDRESEN PL, 1988, 1988 INT COOP GROUP
  • [5] ANGUS JC, 1984, P INT S HONORING M P, P109
  • [6] INHIBITIVE EFFECT OF BENZOTRIAZOLE ON STRESS-CORROSION CRACKING OF ALPHA-BRASS IN MATTSSONS SOLUTION
    ASHWORTH, V
    LYTH, K
    PROCTER, RPM
    [J]. CORROSION, 1979, 35 (04) : 190 - 191
  • [7] BAILEY GL, 1951, J I MET, V79, P243
  • [8] Bain E. C., 1933, T AM SOC STEEL TREAT, V21, P481
  • [9] Bard A., 1980, ELECTROCHEMICAL METH
  • [10] Bard A. J., 1980, ELECTROCHEMICAL METH, P699