The temperature dependence of heavy-ion damage in iron: A microstructural transition at elevated temperatures

Yao, Zhongwen; Jenkins, M. L.; Hernández‐Mayoral, M.; Kirk, Mark A.

doi:10.1080/14786430903430981

Cited by 157 publications

(92 citation statements)

References 24 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…This also results in the growth of a limited number of clusters, and hence a lower DY and a larger loop size. The similar trends of DY vs. temperature and loop size vs. temperature were also recently found in other materials regardless of their different crystal structures, such as in bcc pure Fe [28][29][30][31] and pure W [32][33][34], and in fcc pure Ni [35] and Ni alloys [36].…”

Section: Prismatic Loop Formationsupporting

confidence: 54%

Irradiation Induced Defect Clustering in Zircaloy-2

Yao

Daymond

et al. 2017

Applied Sciences

View full text Add to dashboard Cite

Featured Application: The data and results will be helpful to evaluate the radiation damages in fuel cladding or calandria tube of nuclear power plants.Abstract: The effect of irradiation temperature and alloying elements on defect clustering behaviour directly from the cascade collapse in Zircaloy-2 is examined. The in-situ ioWn irradiation technique was employed to study the formation of -type dislocation loops by Kr ion irradiation at 573 K and 773 K, while the dependence of dislocation loop formationon the presence of alloying elements was investigated by comparing with the defect microstructures of pure Zr irradiated under similar conditions. The experimentally observed temperature dependence of defect clustering was further investigated using molecular dynamics (MD) simulations near the experimental irradiation temperatures. We particularly concentrate on yield and morphology of small defect clusters formed directly from cascade collapse at very low ion doses. Smaller loop size and higher defect yield (DY) in Zircaloy-2 as compared to pure Zr suggests that the presence of the major alloying element Sn increases the number of nucleation sites for the defect clusters but suppresses the point defect recombination. MD simulations at 600 and 800 K revealed that the production of both vacancy and interstitial clusters drops significantly with an increase of irradiation temperature, which is reflected in experimentally collected DY data.

show abstract

Section: Prismatic Loop Formationsupporting

confidence: 54%

Irradiation Induced Defect Clustering in Zircaloy-2

Yao

Daymond

et al. 2017

Applied Sciences

View full text Add to dashboard Cite

show abstract

“…34,35 Other explanations for the presence of 100 loops even at low temperature point to the formation of both 111 and 100 loops in the collision cascade and the growth of these loops by coalescence with small mobile clusters. 33 Note, however, that 100 loops are also observed under low-temperature electron irradiation. 30 All of these open questions result in an incomplete model for defect evolution in α-Fe, and assumptions on the migration of self-interstitial clusters must be made in order to reproduce experimental observations.…”

Section: Kmc Simulations For Damage Accumulationmentioning

confidence: 97%

“…While some experiments point to activation energies of self-interstitial clusters of over 1 eV, 30 simulations predict that these clusters should move almost athermally. 31 Moreover, experiments show the presence of 100 loops in irradiated α-Fe under many different conditions of irradiation (electrons or ions), temperatures, and doses, 30,32,33 even though 111 loops are the lowest energy configuration. At high temperatures (T > 300 • C), the transformation of 111 loops into 100 loops has been observed experimentally 30 and explained theoretically.…”

Section: Kmc Simulations For Damage Accumulationmentioning

confidence: 99%

Influence of the picosecond defect distribution on damage accumulation in irradiatedα-Fe

2012

View full text Add to dashboard Cite

The importance of the defect distribution produced in the first few picoseconds of a collision cascade on long-term damage evolution is studied with molecular dynamics and kinetic Monte Carlo (KMC) methods. Three different interatomic potentials are used to obtain the primary damage produced by energetic recoils in α-Fe. Contrary to previous results, a dependence of cluster-size distribution with recoil energy is obtained. Moreover, large variations in this distribution are observed depending on the interatomic potential. Using the results for 50 keV collision cascades, damage accumulation is modeled with KMC. The accumulation rate of damage visible under transmission electron microscopy predicted by KMC depends significantly on the database used for cascade damage and, therefore, on the interatomic potential. Based on these results, we show that the comparison of cluster-size distributions with experiments can be used to test the reliability of interatomic potentials.

show abstract

“…Also, the loop-plane inclination was confirmed by TEM. 11,18) We have tried various habit planes for the two loops to find the path for the [110]-junction formation. The W 12 values considerably depended on the habit planes.…”

Section: Discussionmentioning

confidence: 99%

“…In α-iron, it has been revealed by molecular dynamics (MD) simulations [5][6][7][8][9] and in-situ TEM experiments, [10][11][12] nanoscale interstitial-type prismatic dislocation loops with b = 1/2 < 111 > undergo one-dimensional (1D) glide diffusion (Brownian motion) along their b directions by thermal energy even in the absence of stresses. Two 1D migrating 1/2 < 111 > loops with different b values and intersecting glide cylinders can collide with each other, via attractive elastic interaction, 13) which has been shown by MD simulations [14][15][16][17] and an in-situ TEM experiment.…”

Section: Introductionmentioning

confidence: 99%

<110> Dislocation Junction Formation via the Coalescence between Nanoscale 1/2<111> Prismatic Dislocation Loops in Iron

et al. 2017

View full text Add to dashboard Cite

Accurate knowledge of dislocation reactions is crucial for understanding and controlling the macroscopic mechanical properties of α-iron and its alloys. A dislocation reaction: 1/2[111] + 1/2[11 1]→[110] has never been observed. However, using in-situ transmission electron microscopy, we demonstrate that the two nanoscale 1/2 <111> prismatic dislocation loops that undergo 1D glide motion approach and collide with each other to form a "high-energy" [110]-dislocation junction. This anomalous reaction cannot be understood within the framework of the elasticity.

show abstract

The temperature dependence of heavy-ion damage in iron: A microstructural transition at elevated temperatures

Cited by 157 publications

References 24 publications

Irradiation Induced Defect Clustering in Zircaloy-2

Irradiation Induced Defect Clustering in Zircaloy-2

Influence of the picosecond defect distribution on damage accumulation in irradiatedα-Fe

<110> Dislocation Junction Formation via the Coalescence between Nanoscale 1/2<111> Prismatic Dislocation Loops in Iron

Contact Info

Product

Resources

About