Primary radiation damage in bcc Fe and Fe–Cr crystals containing dislocation loops

2011 ◽  
Vol 417 (1-3) ◽  
pp. 1063-1066 ◽  
Author(s):  
D. Terentyev ◽  
K. Vörtler ◽  
C. Björkas ◽  
K. Nordlund ◽  
L. Malerba
Keyword(s):  
Radiation Damage ◽  
Primary Radiation ◽  
Dislocation Loops

Annealing Of Radiation Damage in Tungsten

1970 ◽  
Vol 28 ◽  
pp. 412-413
Author(s):  
Robert C. Rau ◽  
John Moteff
Keyword(s):  
Electron Microscopy ◽  
Transmission Electron Microscopy ◽  
Radiation Damage ◽  
Thermal Annealing ◽  
Neutron Fluence ◽  
Dislocation Loops ◽  
Defect Clusters ◽  
Polycrystalline Tungsten ◽  
Transmission Electron ◽  
Radiation Induced

Transmission electron microscopy has been used to study the thermal annealing of radiation induced defect clusters in polycrystalline tungsten. Specimens were taken from cylindrical tensile bars which had been irradiated to a fast (E > 1 MeV) neutron fluence of 4.2 × 1019 n/cm2 at 70°C, annealed for one hour at various temperatures in argon, and tensile tested at 240°C in helium. Foils from both the unstressed button heads and the reduced areas near the fracture were examined.Figure 1 shows typical microstructures in button head foils. In the unannealed condition, Fig. 1(a), a dispersion of fine dot clusters was present. Annealing at 435°C, Fig. 1(b), produced an apparent slight decrease in cluster concentration, but annealing at 740°C, Fig. 1(C), resulted in a noticeable densification of the clusters. Finally, annealing at 900°C and 1040°C, Figs. 1(d) and (e), caused a definite decrease in cluster concentration and led to the formation of resolvable dislocation loops.

Verification of the theory of primary radiation damage by comparison with experimental data

2019 ◽  
Vol 525 ◽  
pp. 22-31 ◽  
Author(s):  
O.V. Ogorodnikova ◽  
M. Majerle ◽  
V.V. Gann ◽  
J. Čížek ◽  
P. Hruška ◽  
...  
Keyword(s):  
Experimental Data ◽  
Radiation Damage ◽  
Primary Radiation ◽  
Comparison With Experimental Data

scholarly journals Microstructure Evolution in ZrCx with Different Stoichiometries Irradiated by Four MeV Au Ions

Materials ◽  
2019 ◽  
Vol 12 (22) ◽  
pp. 3768
Author(s):  
Boxin Wei ◽  
Dong Wang ◽  
Yujin Wang ◽  
Haibin Zhang
Keyword(s):  
Radiation Damage ◽  
Microstructure Evolution ◽  
Vacancy Concentration ◽  
Ion Beam ◽  
Grazing Incidence ◽  
Dislocation Loops ◽  
Black Dot ◽  
X Ray Diffraction ◽  
Near Surface ◽  
Transmission Electron

ZrCx ceramics with different stoichiometries were irradiated under a four MeV Au ion beam in doses of 2 × 1016 ions/cm2 at room temperature, corresponding to ~130 dpa. Grazing incidence, X-ray diffraction and transmission electron microscopy were performed to study the radiation damage and microstructure evolution in ZrCx ceramics. With the decrease in C/Zr ratio, the expansion of ZrCx lattice became smaller after irradiation. Some long dislocation lines formed at the near-surface, while, in the area with the greatest damage (depth of ~400 nm), large amounts of dislocation loops formed in ZrC, ZrC0.9 and ZrC0.8. With the increase in carbon vacancy concentration, the size of the dislocation loops gradually decreased. Few dislocation loops were found in ZrC0.7 after irradiation, and only black-dot defects were found in the area with the greatest damage. For the non-stoichiometric ZrCx, with the increase of the intrinsic vacancies, the number of C interstitials caused by irradiation decreased, and the recombination barrier of C Frenkel pairs reduced. The above factors will reduce the total number of C interstitials after cascade cooling, suppressing the formation and growth of dislocation loops, which is significant for the enhancement of the tolerance of radiation damage.

The effect of PKA directions on the primary radiation damage in the alpha iron nanowires

2019 ◽  
Vol 232 ◽  
pp. 16-22
Author(s):  
Meng Zhang ◽  
Weixiang Peng ◽  
Hongliang Zhang ◽  
Bingjie Wu ◽  
Kun Sun ◽  
...  
Keyword(s):  
Radiation Damage ◽  
Primary Radiation ◽  
Alpha Iron ◽  
Iron Nanowires

scholarly journals Insights into the primary radiation damage of silicon by a machine learning interatomic potential

2020 ◽  
Vol 8 (10) ◽  
pp. 364-372 ◽  
Author(s):  
A. Hamedani ◽  
J. Byggmästar ◽  
F. Djurabekova ◽  
G. Alahyarizadeh ◽  
R. Ghaderi ◽  
...  
Keyword(s):  
Machine Learning ◽  
Radiation Damage ◽  
Interatomic Potential ◽  
Primary Radiation

Dislocation Dynamics Simulation of Interaction between Prismatic Dislocation Loops and Voids in Irradiated Thin Films

2016 ◽  
Vol 725 ◽  
pp. 189-194
Author(s):  
Ying Ying Cai ◽  
Jia Pei Guo ◽  
Yi Ping Chen
Keyword(s):  
Thin Films ◽  
Radiation Damage ◽  
Image Force ◽  
Dislocation Dynamics ◽  
Dynamics Simulation ◽  
Dislocation Loops ◽  
Principle Of Superposition ◽  
Dislocation Glide ◽  
Calculation Results ◽  
Materials Used

At the microscopic scale fast neutron irradiation brings about a high density of small point defect clusters in the form of dislocation loops and voids. And such radiation damage is of primary importance for materials used in nuclear energy production. In the present investigation emphasis is placed on the understanding of the mechanisms involved in the evolution of prismatic dislocation loops by glide in the presence of external free surfaces and those of the voids and in the interaction between dislocation loops and voids within irradiated thin films, so as to simulate in situ Transmission Electron Microscopy (TEM) images of dislocations, which is an indispensable tool for extracting information on radiation damage. By employing 3D dislocation dynamics based on isotropic elacticity and principle of superposition, the calculation results show that the image force is determined by the distance of the dislocation loop from the external and void surfaces and scales with the film thickness; the dislocation glide force is determined by the image stress as well as the loop–loop interaction stress which is in turn governed by the loop spacing. It is also shown that the presence of voids in the thin films has a strong influence on the behaviours of prismatic dislocations.

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