Zirconium alloys are widely used in nuclear reactors as structural materials. During the
operation, they are exposed to fast neutrons. Ion irradiation is used to simulate the damage …

Abstract Samples of annealed Zr-1Nb alloy were deformed under uniaxial compression in
the temperature range of 600–900° C and the strain rate range of 10− 3 to 1s− 1. The strain …

The photo-neutron cross-sections of 93 Nb at the end-point bremsstrahlung energies of 12,
14 and 16 MeV as well as 45, 50, 55, 60 and 70 MeV have been determined by the …

The wear of fuel cladding due to flow induced vibration in nuclear reactor presents a safety
concern, and the impact of neutron irradiation on wear behavior is not fully understood. In …

In this paper the results of experimental study of microstructure changes in Zr–1Nb alloy
after low energy high current pulsed electron beam surface modification and hydrogenation …

To further advance understanding of microstructural evolution in zirconium alloys for high
burnup applications in PWR, it is important to obtain precise characterizations of second …

Zr–1Nb samples were irradiated with 6.37 MeV Xe 26+ ions to 5 dpa at room and high
temperature and the microstructural evolution and mechanical properties were investigated …

Irradiation hardening behavior of Zr–1Nb was examined by nanoindentation, slow positron
annihilation technique, transmission electron microscopy and coplanar extremely …

The cross sections of the^ 96 Zr (n,\2 n)^ 95 Zr 96 Zr (n, 2 n) 95 Zr,^ 90 Zr (n,\2 n)^ 89 Zr 90
Zr (n, 2 n) 89 Zr, and^ 90 Zr 90 Zr (n, 3n)^ 88 Zr 88 Zr reactions with the average neutron …

The present work summarizes the effect of irradiation on the microstructure of Zr–1 wt.% Nb
fuel cladding alloy using 5 MeV proton beam from a Variable Energy Cyclotron. The …