Irradiation-growth in annealed Zr-2.5 wt% Nb at 353 K

Rogerson, A.; Murgatroyd, R.A.

doi:10.1016/0022-3115(79)90189-2

Cited by 19 publications

(2 citation statements)

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“…The literature shows that neutron irradiation may cause the dimensional changes in zirconium in the absence of externally applied stress which is called irradiation growth (14). The irradiation growth has also been extensively studied (15)(16)(17)(18) (19)(20)(21)(22)(23). These studies show that the addition of solute elements in zirconium affects the damage rates when compared with pure zirconium.…”

Section: Introductionmentioning

confidence: 97%

“…It is therefore of fundamental importance to investigate the radiation damage and its effects on the mechanical properties of zirconium. In this regard, various studies were conducted on zirconium and its alloys using electrons (2)(3)(4)(5), ions (6)(7)(8)(9)(10)(11)(12)(13) and neutrons (14)(15)(16)(17)(18)(19)(20) in the past. In most of the studies using heavy ions and electrons irradiation, crystalline to amorphous transitions have been reported (5)(6)(7)10).…”

Section: Introductionmentioning

confidence: 99%

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Mechanical behavior of low-dose neutron-irradiated polycrystalline zirconium

Rafique

Afzal

Ahmad

et al. 2012

Radiation Effects and Defects in Solids

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Samples of polycrystalline zirconium were irradiated with fast neutrons (E > 0.1 MeV) in Pakistan Research Reactor-1 at 423 K to fluences 1.22 × 10 20 , 4.87 × 10 20 and 9.70 × 10 20 n/m 2 . Mechanical properties such as yield stress (YS), ultimate tensile stress (UTS), percentage elongation, stress relaxation rate and hardness of the samples were measured before and after irradiation to analyze post-irradiation effects. The results indicate that neutron irradiation of polycrystalline zirconium does not produce any significant change in its mechanical properties. The YS, UTS and hardness slightly decrease, whereas the percentage elongation increases with an increase in the radiation fluence. Stress relaxation rate was found to be unaffected after irradiation. The post-irradiation microstructure of zirconium reveals that the surface of the material becomes rough by increasing the radiation fluence. X-ray diffraction analysis of the specimens indicates a decrease in the intensity of Bragg's reflection with an increase in the radiation fluence. The insignificant changes in the mechanical properties of zirconium after irradiation are attributed to low defects production in irradiated zirconium and subsequently their recombination due to irradiation temperature.

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