Microstructure and Mechanical Property of Irradiated Zr-2.5Nb Pressure Tube in Wolsong Unit-1

  • 김영숙 (Korea Atomic Energy Research Institute) ;
  • 안상복 (Zirconium Group, Korea atomic Energy Research Institute) ;
  • 오동준 (Zirconium Group, Korea atomic Energy Research Institute) ;
  • 김성수 (Korea Atomic Energy Research Institue.) ;
  • 정용무 (Zirconium Group, Korea atomic Energy Research Institute)
  • Published : 1999.06.01

Abstract

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 306℃ and a neutron fluence of 8.9×$10^{21}$ n/cm²(E>1 MeV) at the maximum. Tensile tests were carried out at temperatures ranging from RT to 300℃. 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 8.9×$10^{21}$ n/cm²(E>1 MeV) yielded an increase in a-type dislocation density of the Zr-2.5Nb pressure tube to 7.5×$10^{14} m^{-2}$, which was highest at the inlet of the tube exposed to the low temperature of 275℃. In contrast, the c-component dislocation density did not change with irradiation, keeping an initial dislocation density of 0.8×$10^{14} m^{-2}$ 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 300℃. The change in the mechanical properties with irradiation is discussed in association with the microstructural change as a function of temperature and neutron fluence.

Keywords

References

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