Zr－4合金的中子辐照生长  

NEUTRON IRRADIATION GROWTH OF ZIRCALOY-4

作　　者：杨继材[1] 任菊艳 

机构地区：[1]中国原子能科学研究院

出　　处：《原子能科学技术》1994年第4期368-372,共5页Atomic Energy Science and Technology

摘　　要：对由两厂分别生产的Ｚｒ－４包壳管样品在重水堆内进行中子辐照试验，辐照温度为６１０Ｋ，快中子注量为４．２×１０￣（２４）ｍ￣（－２）（Ｅ＞１．０ＭｅＶ）。试验结果表明，Ｚｒ－４管的辐照生长应变随辐照中子注量增加呈线性增加。两厂生产的Ｚｒ－４包壳管的生长应变可用Ｇ＝Ａ（φｔ）￣ｎ或Ｇ＝Ｂ＋Ｃ（φｔ）表达式描述，两者的差异可能是合金元素和杂质的综合影响所致。Neutron irradiation growth experiments are carried out on Zircaloy-4 in the HWR Reactor atCIAE. Growh specimens are irradiated in aluminium alloy capsule with argon- filled at tempera-ture 610K.The speciments have reached neutron fluence up to 4.2×10￣(24)m￣(-2)(E>1.0 MeV).The experimental results show that the growth strain is a linear function of flunence.There is apower law relationship:G=A(φt)￣n or a linear relationship:G=B+C(φt),between thegrowth strain(G)and fast neutron fluence. Where A,B,and C are constants.

关 键 词：中子辐照 辐照生长 织构 锆-4合金 

分 类 号：TL341[核科学技术—核技术及应用]