摘要
结合核动力堆用燃料包壳对锆合金耐蚀性能的要求,大范围考察了Nb含量为0.5%,1.0%,2.6%(wt%)的Zr—Nb二元合金及含Cr、Mo、Sn、Bi、Fe、Ce和Si的Zr-1Nb及多元合金,共17种成分的Zr-Nb系合金在400℃,10.3MPa水蒸汽中的长期腐蚀规律(达182天)。在腐蚀转折前,Zr-Nb系合金的腐蚀动力学曲线均近似于抛物线规律,而在转折之后存在与线性规律偏离现象。长期腐蚀增重的分析说明:通过合理的多元合金化,即增加或降低Nb含量,并主加Fe、Bi、Sn和Ni而辅加少量的Cr、Mo、Te和Si,Zr-1Nb合金的耐蚀性大有潜力可挖。
ased on the requirement of corrosion resistance of Zirconium alloys for fuel cladding in nuclear reactors,the long term corrosion behaviour of Zr-Nb binary alloys containing 0.5,1.0 and 2.6Wt% Nb and Zr-1 Nb alloys with Cr,Mo,Sn,Bi,Fe,Te,Ce and Si additives have been examined in 400℃,10.3 MPa Steam.The kinetic curves of all Zr-Nb alloys are close to parabolical law before break-away corrosion.Diviations from linear law are also found in some alloys after break-away cormsion.Analysis of long term corrosion weight gain shows that the corrosion resistance of Zr-1 Nb alloy may be greatly improved by rationally alloying,e·g·increasing or decreasing the content of Nb and adding Fe,Bi,Sn and Ni with the supplement of a little Cr,Mo,Te,and Si.
出处
《稀有金属材料与工程》
SCIE
EI
CAS
CSCD
1995年第3期41-45,共5页
Rare Metal Materials and Engineering