Microstructure and mechanical property of irradiated Zr-2.5Nb pressure tube in Wolsong unit-1

被引:1
|
作者
Kim, YS [1 ]
Ahn, SB [1 ]
Oh, DJ [1 ]
Kim, SS [1 ]
Cheong, YM [1 ]
机构
[1] Korea Atom Energy Res Inst, Zirconium Grp, Yuseong Gu, Taejon 305353, South Korea
来源
METALS AND MATERIALS INTERNATIONAL | 2002年 / 8卷 / 03期
关键词
neutron irradiation; Zr-2.5Nb; pressure tube; a-type dislocation; c-type dislocation; mechanical properties; Wolsong Unit-1;
D O I
10.1007/BF03186091
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
With the aim of assessing the degradation of Zr-2.5Nb pressure tubes operating in the Wolsong unit-1 nuclear power plant, characterization tests are being conducted on irradiated Zr-2.5Nb tubes removed after 10-year operation. The examined tube had been exposed to temperatures ranging from 264 to 306degreesC and a neutron fluence of 8.9x10(21) n/cm(2) (E>1 MeV) at the maximum. Tensile tests were carried out at temperatures ranging from RT to 300degreesC. The density of a-type and c-type dislocations was examined on the irradiated Zr-2.5Nb tube using a transmission electron microscope. Neutron irradiation up to 8.9x10(21) n/cm(2) (E>1 MeV) yielded an increase in a-type dislocation density of the Zr-2.5Nb pressure tube to 7.5x10(14) m(-2), which was highest at the inlet of the tube exposed to the low temperature of 275degreesC. In contrast, the c-component dislocation density did not change with irradiation, keeping an initial dislocation density of 0.8x10(14) m(-2) over the whole length of the tube. As expected, the neutron irradiation increased mechanical strength by about 17-26% in the transverse direction and by 34-39% in the longitudinal direction compared to that of the unirradiated tube at 300degreesC. The change in the mechanical properties with irradiation is discussed in association with the microstructural change as a function of temperature and neutron fluence.
引用
收藏
页码:241 / 246
页数:6
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