EFFECT OF COMPOSITION AND HEAT-TREATMENT ON THE MICROSTRUCTURE AND CORROSION BEHAVIOR OF ZR-NB ALLOYS

被引:66
作者
CHOO, KN
KANG, YH
PYUN, SI
URBANIC, VF
机构
[1] KOREA ADV INST SCI & TECHNOL,DEPT MAT SCI & ENGN,TAEJON,SOUTH KOREA
[2] ATOM ENERGY CANADA LTD,CHALK RIVER K0J 1J0,ONTARIO,CANADA
关键词
D O I
10.1016/0022-3115(94)90256-9
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The influence of Nb content and heat treatment on the structure and isothermal corrosion behavior of Zr-Nb alloys at 300, 360 and 400-degrees-C in static heavy water and steam (1500 psi) are presented. The formation of the martensitic alpha'-phase by beta-quenching treatment results in high weight gains at all test temperatures. Up to 5 wt% Nb, the corrosion resistance of the quenched alloy decreases linearly with increasing Nb content. Through ageing of the beta-quenched specimens, Nb-rich beta-Nb particles are precipitated in the matrix, at twin and alpha'-needle boundaries. The corrosion resistance is greatly improved due to the reduction in Nb supersaturation. The agglomerated large beta-Nb precipitates have detrimental effects on the corrosion resistance as compared to fine precipitates. The corrosion rates of the specimens containing the beta-Zr phase are affected by the Nb content in the beta-Zr phase and seem to show similar weight gains irrespective of the amount of beta-Zr if they form a continuous beta-Zr network. Under the neutron irradiation the corrosion resistance of quenched specimens was sharply improved, but neutron flux had little or no effect on the aged ones.
引用
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页码:226 / 235
页数:10
相关论文
共 21 条
[1]   AGE HARDENING OF ZR-2.5 WT PERCENT NB SLOWLY COOLED FROM (ALPHA+BETA) PHASE FIELD [J].
ALDRIDGE, SA ;
CHEADLE, BA .
JOURNAL OF NUCLEAR MATERIALS, 1972, 42 (01) :32-&
[2]   PRECIPITATION IN ZIRCONIUM-NIOBIUM MARTENSITES [J].
BANERJEE, S ;
VIJAYAKAR, SJ ;
KRISHNAN, R .
JOURNAL OF NUCLEAR MATERIALS, 1976, 62 (2-3) :229-239
[3]   OXIDATION PROPERTIES OF A ZIRCONIUM-2.7 W/O NIOBIUM ALLOY IN TEMPERATURE RANGE 300 DEGREES -500 DEGREES C [J].
COWGILL, MG ;
SMELTZER, WW .
JOURNAL OF THE ELECTROCHEMICAL SOCIETY, 1967, 114 (11) :1089-&
[4]  
COX B, 1976, AECL5610 AT EN CAN L
[5]  
COX B, 1960, UKAEA AERER3257 REP
[6]  
COX B, 1963, UKAEA AEREAR4459 REP
[7]  
DALGAARD SB, 1961, AECL1308 AT EN CAN L
[8]  
FRANKLIN DG, 1991, AM SOC TEST MATER, V1132, P3, DOI 10.1520/STP25496S
[9]  
HEHEMANN RF, 1972, CAN METALL QUART, V11, P201
[10]  
Hillner E., 1977, ZIRCONIUM NUCL IND, P211, DOI DOI 10.1520/STP35573S