scholarly journals RADIATION-INDUCED DISLOCATION AND GROWTH BEHAVIOR OF ZIRCONIUM AND ZIRCONIUM ALLOYS – A REVIEW

2013 ◽  
Vol 45 (3) ◽  
pp. 385-392 ◽  
Author(s):  
SANG IL CHOI ◽  
JI HYUN KIM
Keyword(s):  
Zirconium Alloys ◽  
Growth Behavior ◽  
Radiation Induced ◽  
Induced Dislocation

scholarly journals Homogenization and Growth Behavior of Second-Phase Particles in a Deformed Zr–Sn–Nb–Fe–Cu–Si–O Alloy

Metals ◽  
2018 ◽  
Vol 8 (10) ◽  
pp. 759 ◽  
Author(s):  
Liang-Yu Chen ◽  
Peng Sang ◽  
Lina Zhang ◽  
Dongpo Song ◽  
Yan-Qiu Chu ◽  
...  
Keyword(s):  
Ostwald Ripening ◽  
Short Circuit ◽  
Zirconium Alloys ◽  
Lattice Diffusion ◽  
Growth Behavior ◽  
Homogeneous Distribution ◽  
Second Phase ◽  
Deformation Degree ◽  
Linear Distribution ◽  
Second Phase Particles

Homogeneous distribution of fine second-phase particles (SPPs) fabricated by cycles of deformation and annealing in zirconium alloys is a critical consideration for the corrosion resistance of fuel claddings. Different deformation degrees of zirconium alloys would result in distinctive microstructures, leading to a distinct growth of SPPs during subsequent annealing. Unfortunately, the homogenization and growth behavior of SPPs in deformed zirconium alloys have not been well studied. In this work, a β-quenched Zr–Sn–Nb–Fe–Cu–Si–O alloy was rolled and annealed at 580 °C or 680 °C. The morphologies, distributions, and sizes of SPPs resulting from the different processing procedures were investigated. A linear distribution of SPPs is found in the β-quenched sample. Afterward, SPPs grow and are randomly distributed during heat treatment as the deformation degree or annealing time (or temperature) increases. The homogenization and growth of SPPs are attributed to the Ostwald ripening mechanism that is governed by lattice diffusion and short-circuit diffusion. The sample with a higher deformation degree is speculated to have a larger number of defects that provide more shortcuts for the mass transfer of SPPs, thereby facilitating a homogeneous distribution of fine SPPs during annealing.

Effect of Oversized Alloying Elements on Damage Rates and Recovery in Zirconium

2009 ◽  
Vol 1215 ◽  
Author(s):  
Valeriy Borysenko ◽  
Yuri Petrusenko ◽  
Dmitro Barankov
Keyword(s):  
Rare Earth ◽  
Zirconium Alloys ◽  
Recovery Stage ◽  
Recovery Processes ◽  
Defect Accumulation ◽  
Radiation Resistant ◽  
Radiation Induced ◽  
The Difference ◽  
Dopant Atoms

AbstractStudies were made into the influence of oversized rare-earth atoms on the processes of radiation defect accumulation and annealing in two-component zirconium alloys. Zr and Zr-X alloys (where X = Sc, Dy, Y, Gd and La) have been irradiated with 2 MeV electrons at 82 K. The radiation-induced resistivity has been measured in situ as a function of dose. As compared to unalloyed zirconium, the alloys have exhibited a decrease in the resistivity gain, this decrease being proportional to both the concentration and the size of dopant atoms. A possible explanation for the effect is offered. The difference between the recovery processes in zirconium and in its alloys has been studied. To this end, the irradiated specimens were subjected to isochronal annealing at temperatures between 82 and 350 K. It is shown that Dy, Y, Gd and La atoms trap interstitial atoms at stage I of the recovery. The dissociation of interstitial-impurity complexes takes place at stage II. In zirconium alloys with Dy, Y and Gd, splitting of recovery stage III into two substages has been revealed. The Zr-La alloy has not shown this splitting. Isothermal annealing data were used to determine the activation energies of recovery stages, and also to calculate the activation energy spectra for zirconium and its alloys. The oversized atoms of rare-earth metals are shown to interact effectively with both the interstitials and the vacancies in the zirconium matrix. This effect must be taken into account when developing new radiation-resistant Zr-base alloys or modifying the ones already existing.

Radiation induced creep and growth of zirconium alloys

1980 ◽  
Vol 90 (1-3) ◽  
pp. 89-107 ◽  
Author(s):  
E.J. Savino ◽  
C.E. Laciana
Keyword(s):  
Zirconium Alloys ◽  
Radiation Induced

The response to heating of dislocation structures in zircaloy-2 irradiated to high neutron fluences

1984 ◽  
Vol 42 ◽  
pp. 482-483
Author(s):  
R.W. Gilbert
Keyword(s):  
Zirconium Alloys ◽  
Fast Neutrons ◽  
Dislocation Loops ◽  
Candu Reactors ◽  
Dimensional Changes ◽  
High Temperature Water ◽  
Irradiation Growth ◽  
Induced Dislocation ◽  
High Neutron ◽  
Temperature Water

Zirconium alloys have good neutron economy and corrosion resistance in high temperature water and this has led to extensive usage of these alloys in CANDU reactors. However, during neutron irradiation, dimensional changes occur in zirconium components due to the rearrangement of atoms knocked from their lattice sites by fast neutrons. This “irradiation growth” may limit the lifetime of some reactor components and an understanding of the variables that control the process is of commercial importance.It is believed that dislocations and dislocation loops act as sinks for the displaced atoms and thus control the direction and magnitude of the strain through their Burgers vector. A knowledge of the irradiation-induced dislocation structure is therefore required.

Toward a better understanding of the hydrogen impact on the radiation induced growth of zirconium alloys

2013 ◽  
Vol 441 (1-3) ◽  
pp. 222-231 ◽  
Author(s):  
L. Tournadre ◽  
F. Onimus ◽  
J.-L. Béchade ◽  
D. Gilbon ◽  
J.-M. Cloué ◽  
...  
Keyword(s):  
Zirconium Alloys ◽  
Radiation Induced
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