Evolution of the Irradiation Induced Defect Landscape through Dislocation Vacancy Loop Interactions in Tungsten

Soumya Mishra; Suchandrima Das

REVIEW 3 major objections 4 minor 285 references

Evolution of the Irradiation Induced Defect Landscape through Dislocation Vacancy Loop Interactions in Tungsten

T0 review · 3 major / 4 minor · reviewed 2026-08-01 · deepseek-v4-flash

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Pith's one-line read In irradiated tungsten, a passing dislocation can annihilate, weaken, or leave a vacancy loop unchanged, so the strength of the defect evolves with each interaction rather than staying fixed.

desk verdict The MD mechanism map for vacancy-loop interactions in tungsten is new and mostly convincing, but the upscaling to 213 MPa contains an arithmetic inconsistency that makes the quantitative framework untrustworthy as written. read the letter →

arxiv 2607.27375 v1 pith:VKCRGMYK submitted 2026-07-29 cond-mat.mtrl-sci

Soumya Mishra , Suchandrima Das This is my paper · ORCID

classification cond-mat.mtrl-sci

keywords moleculardynamicsvacancyloopsdislocation–defectinteractionsirradiationhardeningtungstenobstaclestrengthevolutiondefectlandscapemesoscalemodelling

verification ladder T0 review T1 audit T2 compute T3 formal

The pith

A machine-rendered reading of the paper's core claim, the machinery that carries it, and where it could break.

The reading

Using molecular dynamics simulations of edge dislocations passing through vacancy loops in tungsten, the paper establishes that these radiation-induced defects are not static obstacles with a fixed strength. For loops whose Burgers vector is parallel to the dislocation, the outcome depends on the intersection position: a centred encounter partially destroys the loop, a top encounter lets the dislocation absorb it entirely, and a bottom encounter transports the loop away without direct contact. Inclined loops instead react via a Burgers-vector fusion that creates a sessile <100> segment, producing roughly sixfold higher pinning that is nearly independent of the intersection point. When the same dislocation meets the remnant defect again, the strength it feels is set by the stability of the remnant: small platelets lose their pinning, while larger inclined loops retain it. The authors convert these atomistic pinning forces into a 213 MPa critical resolved shear stress contribution, arguing that physically based hardening models must track the evolving defect landscape rather than assume a fixed obstacle field.

What carries the argument

The load-bearing objects are vacancy loops in two stable morphologies—open platelets below about 1–3 nm (depending on orientation) and closed prismatic loops above—and the two interaction mechanisms that classify every simulation: 'Interaction I', where the loop pins the dislocation, the dislocation bows, and breaks away leaving a modified remnant; and 'Interaction II', where a Burgers-vector reaction (1/2⟨111⟩ minus 1/2⟨1̄11⟩ to ⟨010⟩) forms a sessile ⟨100⟩ junction segment that pins the dislocation until cross-slip unpins it. The junction reaction is the identity that explains why inclined loops are strong, size-dependent, and intersection-position insensitive, while parallel loops are wea

What would settle it

Compute the <100> junction binding energy between a 1/2<111> edge dislocation and a 1/2<-111> vacancy loop with density-functional theory and compare with the empirical potential; a large discrepancy would show the 'Interaction II' strong-pinning mechanism is a potential artifact. Complementary: in-situ transmission electron microscopy of irradiated tungsten subjected to controlled deformation should show that inclined loops survive while parallel loops are annihilated or transported.

Watch

Extended reading notes

Core claim

On the paper's own terms, the discovery is that a gliding edge dislocation changes the very defect that pins it, and that this change—not the original loop—determines what the next dislocation feels. Parallel loops behave according to where the dislocation hits them: a centre intersection leaves a shrunken vacancy cluster that pins again at roughly 39–86% lower force; a top intersection absorbs the loop into a superjog and eliminates the obstacle entirely; a bottom intersection pushes the loop ahead of the dislocation without contact, transporting it along the glide cylinder. Inclined loops follow a different route: the dislocation reacts with the loop to form a sessile <100> segment, which

Load-bearing premise

The entire mechanism and strength hierarchy rests on a single empirical interatomic potential for tungsten whose accuracy for vacancy-loop stability, dislocation core structure, and sessile <100> junction energetics is not tested against quantum-mechanical data; if that potential is wrong in these energies, the predicted pathways and the sixfold pinning ratio would change.

Editorial extensions

If this is right

For parallel vacancy loops, a single dislocation passage can annihilate the obstacle (top intersection), convert it into a weaker vacancy cluster (centre), or carry it away without pinning (bottom); the same loop population therefore contains obstacles on different evolutionary trajectories.
Inclined vacancy loops pin dislocations roughly six times more strongly than parallel loops of the same size, with almost no sensitivity to intersection position, so any hardening law that ignores loop orientation will misestimate both the magnitude and the persistence of strengthening.
Repeated dislocation passage shows that 1 nm platelets lose their strengthening after one interaction while 2–10 nm inclined loops keep theirs: obstacle persistence is governed by the stability of the remnant, not the initial loop strength.
The atomistic pinning forces, combined with experimental loop densities, yield an irradiation-induced CRSS contribution of about 213 MPa, close to a previous 260 MPa estimate but through a physically explicit, size- and orientation-dependent path.
The claimed mechanism implies that irradiation softening is the collective result of annihilation, weakening, and persistence pathways, not simply defect removal, and can only be predicted by constitutive laws that evolve the defect population.

Reading between the lines

Editorial extensions of the paper, not claims the author makes directly.

The upscaling relies on an inferred packing factor of about 10^-3, three orders of magnitude below the idealised TEM-based cutting density; this factor is fitted to reproduce the measured 260 MPa hardening, so the 213 MPa output is partly an input. An independent measure of slip-plane loop intersection density would sever that circularity.
If the empirical tungsten potential misrepresents the energy of the sessile <100> junction, the dominant strong-pinning regime for inclined loops could be an artifact; a density-functional calculation of the junction binding energy would settle this.
The paper only treats edge dislocations; at low temperature in BCC tungsten, screw dislocations control plasticity, and their interaction with vacancy loops (including their own junction reactions) could reorder the mechanism hierarchy found here.
A natural testable extension is to deform ion-implanted tungsten in situ in a transmission electron microscope and count the fraction of vacancy loops that survive, transform into clusters, or are transported by dislocations; the predicted survival fractions differ sharply between parallel and inclined loops.

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Editorial analysis

A structured set of objections, weighed in public.

Desk editor's note, referee report, and a circularity audit.

Desk Editor's Note

read the letter

Two things you should know about arXiv:2607.27375. First, the core is genuinely good: it is the first systematic MD study of edge-dislocation–vacancy-loop interactions in tungsten, covering loop size, orientation, and intersection position, and it explicitly addresses what happens when a dislocation passes repeatedly. The mechanism classification—parallel loops being absorbed or transformed, inclined loops forming sessile <100> junctions—is internally consistent and connects sensibly to the interstitial-loop literature where that is relevant. That part is worth reading.

Second, the upscaling in Section 3.4 has a real problem. The authors derive an effective cutting density of 15.3×10^10 m^-2 by matching the 260 MPa experimental hardening with the weakest pinning force (0.18 μN for the 5 nm parallel loop). They then say this corresponds to α = 10^-3. But their own Eq. (5) defines ρ_cut_i,eff = α ρ_cut_i. With ρ_cut_total = 8.81×10^10 m^-2, matching 260 MPa requires α ≈ 1.7, not 10^-3. If you actually apply α = 10^-3 to Table 6, the total hardening is tens of MPa, not 213 MPa. They appear to have divided by the volumetric loop density (6.07×10^13 m^-3) when computing α, then used that value as a factor on areal densities. So the reported 213 MPa cannot be reproduced from the stated equations. Conclusion 5 and the quantitative framework should not be taken at face value.

There are lesser issues too: single trajectories per condition, so no statistical error bars; no validation of the Bonny potential against ab initio data for loop stability, core structure, or the <100> junction; and no input files or trajectories deposited. Those are standard and fixable.

The mechanistic conclusions (1–4) stand independently of the upscaling error. So the paper does deserve a serious referee, but the referee should be alerted to the arithmetic. I would bring it to a reading group for the MD results, and also as a cautionary example of how a unit-scale mistake can sink a multiscale claim.

Referee Report

3 major / 4 minor

Summary. This paper reports molecular dynamics simulations of edge dislocation interactions with vacancy loops in tungsten, varying loop size (1–10 nm), Burgers vector orientation (parallel vs inclined), intersection position (top/centre/bottom), and repeated dislocation passage. It identifies distinct interaction mechanisms: parallel loops undergo absorption, transformation into remnant vacancy clusters, or transport depending on intersection geometry, while inclined loops form sessile <100> junction segments that pin more strongly and are largely insensitive to intersection position. It then proposes an upscaling framework that combines size- and orientation-resolved MD pinning forces with experimental loop densities to estimate a depth-averaged irradiation-induced CRSS contribution of 213 MPa.

Significance. The mechanistic MD results are a valuable systematic contribution: the paper explicitly treats vacancy loops as evolving obstacles, uses a repeated-pass protocol to probe remnant-defect strength, and compares with prior interstitial-loop studies. The identification of intersection-position-dependent pathways (annihilation, weakening, persistence/transport) is a concrete advance over static-obstacle descriptions and provides a useful template for future constitutive laws. The upscaling section, however, contains a serious numerical inconsistency that currently undermines the quantitative framework and Conclusion 5. If the mechanistic claims survive potential-validation and sampling scrutiny, the paper would merit publication in a materials-science journal; as written, the quantitative claim needs major correction.

major comments (3)

[§3.4, Eq. (4)–(5), Table 6] The stated numbers are internally inconsistent. The text gives ρ_cut_total = 8.81×10^10 m^-2, yet says Eq. (4) with F=0.18 μN and τ=260 MPa yields ρ_cut_eff = 15.3×10^10 m^-2 and then assigns α=10^-3. Using b=0.273 nm, Eq. (4) actually requires ρ_cut_eff ≈1.55×10^11 m^-2, so the implied packing factor is α≈1.7, not 10^-3. If α=10^-3 is applied to the stated total, the effective density becomes 8.81×10^7 m^-2 and the 5 nm parallel-loop contribution is roughly 6 MPa, not the reported 213 MPa. The table also mixes powers of ten: ρcut_i is labelled ×10^13 but the text sums it to ×10^10. Please re-derive the upscaling with consistent units and corrected α, or remove the quantitative 213 MPa claim from Conclusion 5.
[§2 and Fig. 7] All mechanistic classifications and pinning strengths are based on a single trajectory per condition. The error bars in Fig. 7 are derived from different force-averaging windows, not from independent initial-velocity replicas. At 300 K and a strain rate of 10^7 s^-1, near-threshold outcomes (e.g., 1 nm bottom first-pass 0.1 μN vs top no pinning) may be sensitive to thermal fluctuations. Please provide at least a few independent replicas per key condition, or explicitly justify why the observed mechanisms are deterministic at this strain rate.
[§2, interatomic potential] The paper states only that simulations used 'the interatomic potential developed by Bonny et al. (2013)', but the cited reference is titled 'On the mobility of vacancy clusters in reduced activation steels: an atomistic study in the Fe–Cr–W model alloy' and is not obviously a pure-W potential. The authors should clarify the exact pure-W parameterization used and validate its transferability for the quantities that drive the conclusions: vacancy-loop stability/morphology, edge-dislocation core structure, and the <100> junction reaction energetics underlying Interaction II. Without this, the quantitative pinning-force hierarchy is not grounded.

minor comments (4)

[Table 6 and surrounding text] The units in the table header and the text sums need reconciliation: ρi, ρcut_i, and ρcut_eff_i appear to use different powers of ten (×10^13, ×10^10, etc.). Please use a single consistent set of units and verify the sums.
[§3.1.2, Fig. 3/4] The centre-interaction force curve is described as 'shown in red in Figure 4(d)', but Figure 4(d) is presented for the top/bottom interactions. Please clarify the cross-reference or include the centre curve in the correct panel.
[Appendix B caption] The caption refers to 'the dotted red curve in Figure 2 (e)', but the force-vs-time panel is Figure 2 (h).
[Throughout] Minor typographical issues: 'Burger vectors' in Table 1 should be 'Burgers vectors'; 'the dislocation meets the loops' in §3.2.2; 'Acknowlegments' in the heading; and the notation τ0H is inconsistently typeset.

Circularity Check

1 steps flagged · score 6.0 of 10

Upscaling α is calibrated to the 260 MPa experimental hardening and then used to compute the 213 MPa CRSS; the mechanistic MD conclusions remain independent.

fitted input called prediction [Section 3.4, Eqs. (4)-(6), Table 6, Figure 8(b); text after Eq. (5)]
"Using the experimentally inferred irradiation hardening of approximately 260 MPa (Das et al. (2020)) together with the lower bound of the atomistically determined pinning strengths (corresponding to the 5 nm parallel loop), Equation 4 yields an effective cutting density of ρcut_eff = 15.3×10^10 loops,m−2. ... This corresponds to an effective packing factor of approximately α=10−3 ... Thus, α=10−3 is used to determine the effective cutting density for each loop-size class."

The packing factor α is not independently measured or derived; it is obtained by inverting Eq. (4) against the 260 MPa experimental hardening using the weakest MD pinning force. The same α is then inserted into Eq. (5) for every size class and combined with Eq. (4) and the SRIM profile to produce the depth-dependent hardening, whose depth-weighted average is reported as 213 MPa. The 'agreement' between 213 and 260 MPa is therefore not an independent validation of the framework: the scale factor was already forced to reproduce 260 MPa at the reference state. Moreover, the printed numbers are internally inconsistent: α=10^-3 applied to ρ_cut_total=8.81×10^10 m^-2 gives 8.8×10^7 m^-2, while matching 260 MPa with F=0.18 μN requires ρ_cut_eff≈1.53×10^11 m^-2, i.e. α≈1.7. The numerical upscaling

full rationale

The paper's core mechanistic contribution—atomistic identification of size-, orientation-, and intersection-position-dependent interaction pathways (annihilation, remnant transformation, defect transport) and the evolution of obstacle strength under repeated dislocation passage—is self-contained MD simulation work and does not depend on the fitted upscaling parameter. That part is not circular. However, Conclusion 5's quantitative 'framework demonstration' is a fitted-input-called-prediction step. Section 3.4 explicitly calibrates α by requiring Eq. (4), with the weakest MD pinning force, to reproduce the experimentally inferred 260 MPa hardening from Das et al. (2020). The same α is then used to compute the effective cutting densities and the final depth-weighted CRSS of 213 MPa. Since α was chosen to make the reference hardening match, the subsequent numerical agreement is substantially forced by construction rather than an independent test of the upscaling framework. The text also contains an internal inconsistency between α=10^-3 and the quoted ρ_cut_eff=15.3×10^10 m^-2 (matching 260 MPa with F=0.18 μN requires α≈1.7), which further undermines the reported 213 MPa as a reproducible calculation, though this is primarily a correctness issue. No other load-bearing circularity was found: the self-citations to Das et al. (2020, 2024) provide experimental data, prior derivation of loop cutting densities, and simulation setup details, not a uniqueness theorem or an unverified ansatz that the central mechanism claims depend on. Overall score 6 reflects one central quantitative prediction reducing to calibration while the mechanistic conclusions remain independent.

Assumptions & free parameters 3 free parameters · 5 assumptions · 0 invented entities

The mechanistic core is a simulation on one empirical potential, with loop morphology taken from prior energetics, edge-only dislocations, and idealized periodic geometry. The quantitative hardening result additionally depends on a fitted packing factor and an assumed 50/50 orientation split. Away from the new MD observations themselves, the paper imports many unverified premises rather than establishing them.

free parameters (3)

Packing factor α = 10^-3
Fitted via Eq. (4)-(5) to match the experimental 260 MPa hardening using the weakest MD pinning force (5 nm parallel loop); then applied across all loop-size classes and depths, so the 213 MPa result inherits this calibration.
Orientation fraction (parallel vs inclined) = 0.5
Assumed half parallel and half inclined because TEM cannot determine loop orientation relative to the active slip system; directly weights the CRSS through the different pinning strengths.
Strain rate = 10^-5 ps^-1 (10^7 s^-1)
Chosen for computational feasibility; Appendix A tests strain-rate dependence only in a loop-free cell, so pinning strengths are assumed to be insensitive to strain rate without direct verification.

assumptions (5)

domain assumption Bonny et al. (2013) W interatomic potential accurately captures vacancy-loop stability, dislocation cores, and reaction energetics.
All MD results in Section 2 rely on this potential; no DFT validation or comparison for the specific defects studied here.
domain assumption Stable loop morphology for each size is the platelet below 1 nm (parallel) or ~3 nm (inclined) and closed loop above, as cited from Gilbert et al. 2008/2014.
Used to choose initial loop structures; if the size-dependent stability map is wrong, the mechanisms assigned to each size regime shift.
domain assumption Edge dislocations are a representative probe of plastic deformation in BCC W despite screw-dislocation-controlled plasticity.
The paper argues edge dislocations are more sensitive to defects, but conclusions about defect-landscape evolution are framed generally rather than edge-specific.
domain assumption Periodic-cell geometry with an isolated loop represents the collective obstacle field in a real irradiated microstructure.
The paper itself acknowledges in Section 3.4 that random loop distributions and sequential obstacle overcoming could lower effective pinning strengths.
standard math Eq. (3)-(4) work-equivalence and linear summation of size-class hardening contributions are valid for translating MD pinning forces to CRSS.
DBH-style relation assumed without a derivation that accounts for simultaneous, randomly positioned obstacles of different strengths.

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Cite this review

Pith. "Pith review of Evolution of the Irradiation Induced Defect Landscape through Dislocation Vacancy Loop Interactions in Tungsten." pith.science (2026). https://pith.science/paper/VKCRGMYK

@misc{pith2026260727375,
  author       = {Pith},
  title        = {Pith review of: Evolution of the Irradiation Induced Defect Landscape through Dislocation Vacancy Loop Interactions in Tungsten},
  year         = {2026},
  howpublished = {\url{https://pith.science/paper/VKCRGMYK}},
  note         = {Machine review of arXiv:2607.27375}
}

read the original abstract

Structural materials for fusion reactors undergo neutron irradiation, generating defect populations that govern their mechanical response through irradiation hardening. Physically based mesoscale constitutive models require accurate descriptions of dislocation defect interactions and, critically, how both defect morphology and obstacle strength evolve during plastic deformation as the irradiation-induced defect landscape changes. Vacancy loops provide an ideal prototype for addressing this problem because they are among the most prevalent irradiation-induced defects in tungsten, yet their interaction mechanisms with dislocations and subsequent evolution remain poorly understood. Molecular dynamics simulations are used to systematically investigate interactions between edge dislocations and vacancy loops in tungsten by varying loop size, crystallographic orientation, and dislocation loop intersection geometry. Parallel loops exhibit strong geometry dependent behaviour, undergoing complete annihilation, transformation into weaker remnant defects, or defect transport depending on the interaction geometry. In contrast, inclined loops interact through Burgers vector reactions that form sessile <100> dislocation segments, producing substantially higher pinning strengths with little sensitivity to the intersection position. Finally, a framework is demonstrated for translating atomistically determined obstacle strengths into constitutive parameters, such as irradiation hardening, for mesoscale models. The mechanistic understanding developed here provides the physical basis for future mesoscale constitutive laws that explicitly account for the evolution of irradiation-induced defect populations and the resulting changes in dislocation-defect interaction mechanisms and obstacle strength, thereby improving predictive capability beyond calibrated conditions.

Figures

Figures reproduced from arXiv: 2607.27375 by the authors.

**Figure 2.** Different stages of the interaction of an [PITH_FULL_IMAGE:figures/full_fig_p014_2.png] view at source ↗

**Figure 3.** Different stages of the interaction of an [PITH_FULL_IMAGE:figures/full_fig_p017_3.png] view at source ↗

Figures from the paper (5 more)

**Figure 4.** Figure 4: Different stages of the interaction of an [PITH_FULL_IMAGE:figures/full_fig_p020_4.png]

**Figure 5.** Figure 5: Different stages of the interaction of an [PITH_FULL_IMAGE:figures/full_fig_p025_5.png]

**Figure 6.** Figure 6: Different stages of the interaction of an [PITH_FULL_IMAGE:figures/full_fig_p028_6.png]

**Figure 7.** Figure 7: Pinning force vs. loop size for the interaction of an 1 2 ⟨111⟩ edge dislocation with vacancy loop in parallel ( 1 2 ⟨111⟩) and inclined ( 1 2 ⟨1¯11⟩) orientations. The error bar on the pinning force is calculated using averaging windows of lengths ranging from 1 ps to…

**Figure 8.** Figure 8: Effective pinning stress as a function of depth in irradiated tungsten(0.01 dpa) [PITH_FULL_IMAGE:figures/full_fig_p039_8.png]

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Reference graph

Works this paper leans on

285 extracted references

[1]

Acta Materialia , volume=

Atomistic insights into the enhancement of dynamic yield and fracture responses by chemical short-range order in CoCrNi multi-principal element alloy under quasi-isentropic loading , author=. Acta Materialia , volume=. 2026 , publisher=

2026
[2]

International Journal of Plasticity , volume=

Experiments and/or crystal plasticity finite element modeling of the mechanical properties of pristine and irradiated tungsten single crystal , author=. International Journal of Plasticity , volume=. 2022 , publisher=

2022
[3]

International Journal of Plasticity , volume=

Temperature dependent deformation localization in irradiated tungsten , author=. International Journal of Plasticity , volume=. 2021 , publisher=

2021
[4]

International Journal of Plasticity , volume=

Atomic irradiation defects induced hardening model in irradiated tungsten based on molecular dynamics and CPFEM , author=. International Journal of Plasticity , volume=. 2024 , publisher=

2024
[5]

International Journal of Plasticity , volume=

Dislocation motion in tungsten: atomistic input to discrete dislocation simulations , author=. International Journal of Plasticity , volume=. 2013 , publisher=

2013
[6]

Acta Materialia , volume=

A phenomenological dislocation mobility law for bcc metals , author=. Acta Materialia , volume=. 2016 , publisher=

2016
[7]

Nature Communications , volume=

Repulsion leads to coupled dislocation motion and extended work hardening in bcc metals , author=. Nature Communications , volume=. 2020 , publisher=

2020
[8]

Materials Science and Engineering: A , volume=

A mechanism-based quantitative multi-scale framework for investigating irradiation hardening of tungsten at low temperature , author=. Materials Science and Engineering: A , volume=. 2020 , publisher=

2020

Show all 285 references

[9]

Journal of Nuclear Materials , volume=

Irradiation hardening of pure tungsten exposed to neutron irradiation , author=. Journal of Nuclear Materials , volume=. 2016 , publisher=

2016
[10]

Metallurgical and Materials Transactions A , volume=

Analysis of obstacle hardening models using dislocation dynamics: application to irradiation-induced defects , author=. Metallurgical and Materials Transactions A , volume=. 2015 , publisher=

2015
[11]

Philosophical Magazine , volume=

Brittle--ductile transitions in polycrystalline tungsten , author=. Philosophical Magazine , volume=. 2010 , publisher=

2010
[12]

Journal of Nuclear Materials , volume=

Deformation localisation in ion-irradiated Fe and Fe10Cr , author=. Journal of Nuclear Materials , volume=. 2024 , publisher=

2024
[13]

International Journal of Plasticity , volume=

Strain localization and failure in irradiated zircaloy with crystal plasticity , author=. International Journal of Plasticity , volume=. 2015 , publisher=

2015
[14]

International Journal of Plasticity , volume=

Nanoindentation study of -phase zirconium hydride using the crystal plasticity model , author=. International Journal of Plasticity , volume=. 2023 , publisher=

2023
[15]

International Journal of Plasticity , volume=

Modelling nano-indentation of ion-irradiated FCC single crystals by strain-gradient crystal plasticity theory , author=. International Journal of Plasticity , volume=. 2019 , publisher=

2019
[16]

International Journal of Plasticity , volume=

Predicting plastic flow and irradiation hardening of iron single crystal with mechanism-based continuum dislocation dynamics , author=. International Journal of Plasticity , volume=. 2014 , publisher=

2014
[17]

Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms , volume=

TEM observations of radiation damage in tungsten irradiated by 20 MeV W ions , author=. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms , volume=. 2013 , publisher=

2013
[18]

Journal of Nuclear Materials , volume=

The response of polycrystalline tungsten to 30 keV helium ion implantation at normal incidence and high temperatures , author=. Journal of Nuclear Materials , volume=. 2012 , publisher=

2012
[19]

Materials Characterization , volume=

High-temperature damage evolution in 10 keV He+ irradiated W and W-5Re , author=. Materials Characterization , volume=. 2018 , publisher=

2018
[20]

Journal of Nuclear Materials , volume=

First temperature stage evolution of irradiation-induced defects in tungsten studied by positron annihilation spectroscopy , author=. Journal of Nuclear Materials , volume=. 2008 , publisher=

2008
[21]

Physical Review Letters , volume=

Observation of transient and asymptotic driven structural states of tungsten exposed to radiation , author=. Physical Review Letters , volume=. 2020 , publisher=

2020
[22]

Acta Materialia , volume=

In-situ TEM investigation of 30 keV he+ irradiated tungsten: Effects of temperature, fluence, and sample thickness on dislocation loop evolution , author=. Acta Materialia , volume=. 2021 , publisher=

2021
[23]

Acta Materialia , volume=

Trends in vacancy distribution and hardness of high temperature neutron irradiated single crystal tungsten , author=. Acta Materialia , volume=. 2020 , publisher=

2020
[24]

Journal of Nuclear Materials , volume=

Annealing of radiation-induced defects in tungsten: positron annihilation spectroscopy study , author=. Journal of Nuclear Materials , volume=. 2019 , publisher=

2019
[25]

Physical Review Materials , volume=

Nanoscale imaging of the full strain tensor of specific dislocations extracted from a bulk sample , author=. Physical Review Materials , volume=. 2020 , publisher=

2020
[26]

Synchrotron Radiation , volume=

Bragg coherent diffraction imaging and metrics for radiation damage in protein micro-crystallography , author=. Synchrotron Radiation , volume=. 2017 , publisher=

2017
[27]

International Journal of Plasticity , volume=

Towards a reliable nanohardness-dose correlation of ion-irradiated materials from nanoindentation tests: A case study in proton-irradiated vanadium , author=. International Journal of Plasticity , volume=. 2023 , publisher=

2023
[28]

Philosophical magazine , volume=

Determination of elastic strain fields and geometrically necessary dislocation distributions near nanoindents using electron back scatter diffraction , author=. Philosophical magazine , volume=. 2010 , publisher=

2010
[29]

Ultramicroscopy , volume=

Measurement of geometrically necessary dislocation density with high resolution electron backscatter diffraction: Effects of detector binning and step size , author=. Ultramicroscopy , volume=. 2013 , publisher=

2013
[30]

Journal of Nuclear Materials , volume=

Effects of neutron irradiation on the brittle to ductile transition in single crystal tungsten , author=. Journal of Nuclear Materials , volume=. 2019 , publisher=

2019
[31]

Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms , volume=

Molecular dynamics simulation of vacancy diffusion in tungsten induced by irradiation , author=. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms , volume=. 2003 , publisher=

2003
[32]

Materials Chemistry and Physics , volume=

Microstructure and defect evolution in oxygen ion-irradiated pure nickel--Insights from experimental probes and molecular dynamics simulations , author=. Materials Chemistry and Physics , volume=. 2023 , publisher=

2023
[33]

Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms , volume=

Pressure of stable He--vacancy complex in bcc iron: Molecular dynamics simulations , author=. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms , volume=. 2009 , publisher=

2009
[34]

Journal of Physics: Conference Series , volume=

Simulation of interaction of edge dislocations with radiation defects in Fe-10Cr alloy , author=. Journal of Physics: Conference Series , volume=. 2018 , organization=

2018
[35]

Physical review letters , volume=

Dislocation pinning by small interstitial loops: a molecular dynamics study , author=. Physical review letters , volume=. 1999 , publisher=

1999
[36]

Materialia , volume=

Coupled cluster-dislocation dynamics of irradiation-induced defects , author=. Materialia , volume=. 2020 , publisher=

2020
[37]

Philosophical Magazine , volume=

The obstacles responsible for the hardening of neutron irradiated copper crystals , author=. Philosophical Magazine , volume=. 1968 , publisher=

1968
[38]

lattice” hardening in irradiated copper crystals with the external characteristics of “source

A model of “lattice” hardening in irradiated copper crystals with the external characteristics of “source” hardening , author=. physica status solidi (b) , volume=. 1965 , publisher=

1965
[39]

Journal of Nuclear Materials , volume=

Mechanical properties of single-crystal tungsten irradiated in a mixed spectrum fission reactor , author=. Journal of Nuclear Materials , volume=. 2019 , publisher=

2019
[40]

Nuclear Physics A , volume=

Investigation of radiation damage in stainless steel, tungsten and tantalum by heavy ion irradiations , author=. Nuclear Physics A , volume=. 2010 , publisher=

2010
[41]

Journal of nuclear materials , volume=

Hydrogen and helium trapping in tungsten under simultaneous irradiations , author=. Journal of nuclear materials , volume=. 2007 , publisher=

2007
[42]

Scripta Materialia , volume=

Decoration of voids with rhenium and osmium transmutation products in neutron irradiated single crystal tungsten , author=. Scripta Materialia , volume=. 2019 , publisher=

2019
[43]

2011 , publisher=

Introduction to dislocations , author=. 2011 , publisher=

2011
[44]

Scripta Materialia , volume=

Revealing the synergistic effect of invisible helium clusters in helium irradiation hardening in tungsten , author=. Scripta Materialia , volume=. 2022 , publisher=

2022
[45]

Nuclear Fusion , volume=

Unveiling the inhibitory effect of hydrogen-decorated voids and dislocation loops on the glide of edge dislocation in tungsten , author=. Nuclear Fusion , volume=. 2025 , publisher=

2025
[46]

Scripta Materialia , volume=

Influence of rhenium-decorated dislocation loops on edge dislocation gliding in tungsten , author=. Scripta Materialia , volume=. 2023 , publisher=

2023
[47]

Tungsten , volume=

Atomic-scale mechanisms of void strengthening in tungsten , author=. Tungsten , volume=. 2021 , publisher=

2021
[48]

International Journal of Plasticity , volume=

The dislocation behaviour and GND development in a nickel based superalloy during creep , author=. International Journal of Plasticity , volume=. 2019 , publisher=

2019
[49]

Nano Letters , volume=

New Insight into the Quantifying Vacancy Distribution in Self-Ion-Irradiated Tungsten: A Combined Experimental and Computational Study , author=. Nano Letters , volume=. 2025 , publisher=

2025
[50]

Journal of Nuclear Materials , volume=

Effect of purity on the vacancy defects induced in self--irradiated tungsten: A combination of PAS and TEM , author=. Journal of Nuclear Materials , volume=. 2021 , publisher=

2021
[51]

Science advances , volume=

Mapping pure plastic strains against locally applied stress: Revealing toughening plasticity , author=. Science advances , volume=. 2022 , publisher=

2022
[52]

Journal of Nuclear Materials , volume=

Short positron lifetime at vacancies observed in electron-irradiated tungsten: Experiments and first-principles calculations , author=. Journal of Nuclear Materials , volume=. 2020 , publisher=

2020
[53]

Journal of Nuclear Materials , volume=

Comparative study of deuterium retention and vacancy content of self-ion irradiated tungsten , author=. Journal of Nuclear Materials , volume=. 2022 , publisher=

2022
[54]

International Journal of Refractory Metals and Hard Materials , volume=

Positron annihilation spectroscopy investigation of defects in neutron irradiated tungsten materials , author=. International Journal of Refractory Metals and Hard Materials , volume=. 2022 , publisher=

2022
[55]

Journal of Nuclear Materials , volume=

New perspectives on collision cascade damage in self-ion irradiated tungsten from HR-EBSD and ECCI , author=. Journal of Nuclear Materials , volume=. 2021 , publisher=

2021
[56]

Acta Materialia , volume=

3D HR-EBSD Characterization of the plastic zone around crack tips in tungsten single crystals at the micron scale , author=. Acta Materialia , volume=. 2020 , publisher=

2020
[57]

Materials Science and Engineering: A , volume=

Effect of dislocation density on improved radiation hardening resistance of nano-structured tungsten--rhenium , author=. Materials Science and Engineering: A , volume=. 2014 , publisher=

2014
[58]

Scripta Materialia , volume=

Elastic strain associated with irradiation-induced defects in self-ion irradiated tungsten , author=. Scripta Materialia , volume=. 2023 , publisher=

2023
[59]

Physica Scripta , volume=

Development of positron annihilation spectroscopy for characterizing neutron irradiated tungsten , author=. Physica Scripta , volume=. 2014 , publisher=

2014
[60]

Nuclear Materials and Energy , volume=

Neutron irradiated tungsten bulk defect characterization by positron annihilation spectroscopy , author=. Nuclear Materials and Energy , volume=. 2021 , publisher=

2021
[61]

Tungsten , volume=

Recent progress of radiation response in nanostructured tungsten for nuclear application , author=. Tungsten , volume=. 2021 , publisher=

2021
[62]

Scripta Materialia , volume=

Effect of dose rate on dislocation loop evolution in tungsten: combination of defect generation rate and elastic interaction , author=. Scripta Materialia , volume=. 2023 , publisher=

2023
[63]

Nature communications , volume=

Revealing nano-scale lattice distortions in implanted material with 3D Bragg ptychography , author=. Nature communications , volume=. 2021 , publisher=

2021
[64]

Journal of Nuclear Materials , volume=

Neutron irradiation effects on the microstructural development of tungsten and tungsten alloys , author=. Journal of Nuclear Materials , volume=. 2016 , publisher=

2016
[65]

Fusion Engineering and Design , volume=

Neutron irradiation effects on tungsten materials , author=. Fusion Engineering and Design , volume=. 2014 , publisher=

2014
[66]

Acta Materialia , volume=

Unprecedented irradiation resistance of nanocrystalline tungsten with equiaxed nanocrystalline grains to dislocation loop accumulation , author=. Acta Materialia , volume=. 2019 , publisher=

2019
[67]

Scientific Reports , volume=

Impact of interstitial impurities on the trapping of dislocation loops in tungsten , author=. Scientific Reports , volume=. 2021 , publisher=

2021
[68]

Modelling and Simulation in Materials Science and Engineering , volume=

The influence of interaction geometry on the obstacle strength of voids and copper precipitates in iron , author=. Modelling and Simulation in Materials Science and Engineering , volume=
[69]

Modelling and simulation in materials science and engineering , volume=

Atomistic-object kinetic Monte Carlo simulations of irradiation damage in tungsten , author=. Modelling and simulation in materials science and engineering , volume=. 2019 , publisher=

2019
[70]

Journal of Nuclear Materials , volume=

Understanding why dislocation loops are visible in transmission electron microscopy: The tungsten case , author=. Journal of Nuclear Materials , volume=. 2021 , publisher=

2021
[71]

Philosophical magazine , volume=

Atomic modelling of strengthening mechanisms due to voids and copper precipitates in -iron , author=. Philosophical magazine , volume=. 2003 , publisher=

2003
[72]

Journal of Physics: Condensed Matter , volume=

On the mobility of vacancy clusters in reduced activation steels: an atomistic study in the Fe--Cr--W model alloy , author=. Journal of Physics: Condensed Matter , volume=. 2013 , publisher=

2013
[73]

Acta Materialia , volume=

Materials challenges in nuclear energy , author=. Acta Materialia , volume=. 2013 , publisher=

2013
[74]

Materials Transactions , volume=

Effects of transmutation elements on neutron irradiation hardening of tungsten , author=. Materials Transactions , volume=. 2007 , publisher=

2007
[75]

Materials transactions , volume=

Neutron irradiation behavior of tungsten , author=. Materials transactions , volume=. 2013 , publisher=

2013
[76]

Acta Materialia , volume=

In-situ TEM studies of 150 keV W+ ion irradiated W and W-alloys: Damage production and microstructural evolution , author=. Acta Materialia , volume=. 2016 , publisher=

2016
[77]

Materials Characterization , volume=

In-situ TEM/heavy ion irradiation on ultrafine-and nanocrystalline-grained tungsten: Effect of 3 MeV Si, Cu and W ions , author=. Materials Characterization , volume=. 2015 , publisher=

2015
[78]

Applied Physics Letters , volume=

Effects of sequential tungsten and helium ion implantation on nano-indentation hardness of tungsten , author=. Applied Physics Letters , volume=. 2013 , publisher=

2013
[79]

Plasma and Fusion Research , volume=

First-principles study on migration of vacancy in tungsten , author=. Plasma and Fusion Research , volume=. 2014 , publisher=

2014
[80]

Physical Review Materials , volume=

Multiscale analysis of dislocation loops and voids in tungsten , author=. Physical Review Materials , volume=. 2020 , publisher=

2020
[81]

Nuclear Materials and Energy , volume=

Nano-sized prismatic vacancy dislocation loops and vacancy clusters in tungsten , author=. Nuclear Materials and Energy , volume=. 2018 , publisher=

2018
[82]

Acta Materialia , volume=

Theory of kink migration in dilute BCC alloys , author=. Acta Materialia , volume=. 2021 , publisher=

2021
[83]

Philosophical magazine letters , volume=

Dynamic properties of edge dislocations decorated by interstitial loops in -iron and copper , author=. Philosophical magazine letters , volume=. 2004 , publisher=

2004
[84]

Nuclear Fusion , volume=

Impact of neutron irradiation on hardening of baseline and advanced tungsten grades and its link to initial microstructure , author=. Nuclear Fusion , volume=. 2021 , publisher=

2021
[85]

Materials Science and Engineering: A , volume=

Nanoindentation study on early-stage radiation damage in single-phase concentrated solid solution alloys , author=. Materials Science and Engineering: A , volume=. 2024 , publisher=

2024
[86]

Materials Characterization , volume=

Irradiation-induced strain localization and strain burst suppression investigated by microcompression and concurrent acoustic emission experiments , author=. Materials Characterization , volume=. 2023 , publisher=

2023
[87]

Materialia , volume=

Microstructural evolution and transmutation in tungsten under ion and neutron irradiation , author=. Materialia , volume=. 2024 , publisher=

2024
[88]

Energy , volume=

Approximation of the economy of fusion energy , author=. Energy , volume=. 2018 , publisher=

2018
[89]

Nature Physics , volume=

Materials research for fusion , author=. Nature Physics , volume=. 2016 , publisher=

2016
[90]

Journal of Nuclear Materials , volume=

Hardening of self ion implanted tungsten and tungsten 5-wt\ author=. Journal of Nuclear Materials , volume=. 2013 , publisher=

2013
[91]

Scripta Materialia , volume=

The effect of helium implantation on the deformation behaviour of tungsten: X-ray micro-diffraction and nanoindentation , author=. Scripta Materialia , volume=. 2018 , publisher=

2018
[92]

Materials & Design , volume=

Helium-implantation-induced lattice strains and defects in tungsten probed by X-ray micro-diffraction , author=. Materials & Design , volume=. 2018 , publisher=

2018
[93]

Journal of materials research , volume=

Hydrogen embrittlement of tungsten induced by deuterium plasma: Insights from nanoindentation tests , author=. Journal of materials research , volume=. 2018 , publisher=

2018
[94]

Acta Materialia , volume=

Thermal diffusivity degradation and point defect density in self-ion implanted tungsten , author=. Acta Materialia , volume=. 2020 , publisher=

2020
[95]

Philosophical Magazine , volume=

In situ study of self-ion irradiation damage in W and W--5Re at 500 C , author=. Philosophical Magazine , volume=. 2013 , publisher=

2013
[96]

Journal of Nuclear Materials , volume=

Predicting neutron damage using TEM with in situ ion irradiation and computer modeling , author=. Journal of Nuclear Materials , volume=. 2018 , publisher=

2018
[97]

Physica Scripta , volume=

Mechanical properties of ion-implanted tungsten--5 wt\ author=. Physica Scripta , volume=
[98]

Materials Science and Engineering: A , volume=

High temperature indentation of helium-implanted tungsten , author=. Materials Science and Engineering: A , volume=. 2015 , publisher=

2015
[99]

Journal of Nuclear Materials , volume=

Ion-irradiation-induced damage in Fe--Cr alloys characterized by nanoindentation , author=. Journal of Nuclear Materials , volume=. 2011 , publisher=

2011
[100]

Acta Materialia , volume=

Detecting self-ion irradiation-induced void swelling in pure copper using transient grating spectroscopy , author=. Acta Materialia , volume=. 2018 , publisher=

2018
[101]

Journal of Nuclear Materials , volume=

Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa , author=. Journal of Nuclear Materials , volume=. 2014 , publisher=

2014
[102]

Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms , volume=

Ion-irradiation-induced damage of steels characterized by means of nanoindentation , author=. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms , volume=. 2009 , publisher=

2009
[103]

Journal of nuclear materials , volume=

Oxygen effects on irradiated tantalum alloys , author=. Journal of nuclear materials , volume=. 2009 , publisher=

2009
[104]

2016 , institution=

Quantifying irradiation defects in zirconium alloys: a comparison between transmission electron microscopy and whole-pattern diffraction line-profile analysis-2016-0089 , author=. 2016 , institution=

2016
[105]

Journal of Nuclear Materials , volume=

Accumulation of dislocation loops in the phase of Zr Excel alloy under heavy ion irradiation , author=. Journal of Nuclear Materials , volume=. 2017 , publisher=

2017
[106]

Philosophical Magazine , volume=

Study of defect evolution by TEM with in situ ion irradiation and coordinated modeling , author=. Philosophical Magazine , volume=. 2012 , publisher=

2012
[107]

Journal of Nuclear Materials , volume=

He ion irradiation damage in Fe/W nanolayer films , author=. Journal of Nuclear Materials , volume=. 2009 , publisher=

2009
[108]

Nature , volume=

Atomistic mechanisms governing elastic limit and incipient plasticity in crystals , author=. Nature , volume=. 2002 , publisher=

2002
[109]

Acta materialia , volume=

Orientation dependence of nanoindentation pile-up patterns and of nanoindentation microtextures in copper single crystals , author=. Acta materialia , volume=. 2004 , publisher=

2004
[110]

International Journal of Plasticity , volume=

Orientation-dependent irradiation hardening in pure Zr studied by nanoindentation, electron microscopies, and crystal plasticity finite element modeling , author=. International Journal of Plasticity , volume=. 2020 , publisher=

2020
[111]

Nuclear Engineering and technology , volume=

Strain localization in irradiated materials , author=. Nuclear Engineering and technology , volume=. 2006 , publisher=

2006
[112]

Scripta Materialia , volume=

Temperature dependence of helium-implantation-induced lattice swelling in polycrystalline tungsten: X-ray micro-diffraction and Eigenstrain modelling , author=. Scripta Materialia , volume=. 2015 , publisher=

2015
[113]

Journal of materials research , volume=

Measurement of hardness and elastic modulus by instrumented indentation: Advances in understanding and refinements to methodology , author=. Journal of materials research , volume=. 2004 , publisher=

2004
[114]

Ultramicroscopy , volume=

Measurement of elastic strains and small lattice rotations using electron back scatter diffraction , author=. Ultramicroscopy , volume=. 1996 , publisher=

1996
[115]

International Journal of Plasticity , volume=

Crystal plasticity modelling and HR-DIC measurement of slip activation and strain localization in single and oligo-crystal Ni alloys under fatigue , author=. International Journal of Plasticity , volume=. 2017 , publisher=

2017
[116]

Journal of Nuclear Materials , volume=

Recent progress in research on tungsten materials for nuclear fusion applications in Europe , author=. Journal of Nuclear Materials , volume=. 2013 , publisher=

2013
[117]

Materials Science and Technology , volume=

Predicting the performance of tungsten in a fusion environment: a literature review , author=. Materials Science and Technology , volume=. 2017 , publisher=

2017
[118]

Acta Materialia , volume=

Lattice swelling and modulus change in a helium-implanted tungsten alloy: X-ray micro-diffraction, surface acoustic wave measurements, and multiscale modelling , author=. Acta Materialia , volume=. 2015 , publisher=

2015
[119]

Journal of Nuclear Materials , volume=

Microstructural examination of neutron, proton and self-ion irradiation damage in a model Fe9Cr alloy , author=. Journal of Nuclear Materials , volume=. 2020 , publisher=

2020
[120]

AIP Advances , volume=

First-principles study of the phase stability and the mechanical properties of W-Ta and W-Re alloys , author=. AIP Advances , volume=. 2014 , publisher=

2014
[121]

Nuclear Fusion , volume=

Neutron-induced transmutation effects in W and W-alloys in a fusion environment , author=. Nuclear Fusion , volume=
[122]

Nuclear Fusion , volume=

An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation , author=. Nuclear Fusion , volume=. 2012 , publisher=

2012
[123]

Materials Research Express , volume=

Helium, hydrogen, and fuzz in plasma-facing materials , author=. Materials Research Express , volume=. 2017 , publisher=

2017
[124]

Mrs Bulletin , volume=

Challenges in materials research for sustainable nuclear energy , author=. Mrs Bulletin , volume=. 2008 , publisher=

2008
[125]

MRS Online Proceedings Library (OPL) , volume=

Effect of alloy composition & helium ion-irradiation on the mechanical properties of tungsten, tungsten-tantalum & tungsten-rhenium for fusion power applications , author=. MRS Online Proceedings Library (OPL) , volume=. 2013 , publisher=

2013
[126]

Journal of Nuclear Materials , volume=

Modelling self trapping and trap mutation in tungsten using DFT and Molecular Dynamics with an empirical potential based on DFT , author=. Journal of Nuclear Materials , volume=. 2014 , publisher=

2014
[127]

Physica Scripta , volume=

Molecular dynamics simulation of a helium bubble bursting on tungsten surfaces , author=. Physica Scripta , volume=. 2014 , publisher=

2014
[128]

Philosophical Magazine A , volume=

Quenching and recovery investigations of vacancies in tungsten , author=. Philosophical Magazine A , volume=. 1980 , publisher=

1980
[129]

Journal of nuclear materials , volume=

Deuterium interaction with impurities in tungsten studied with TDS , author=. Journal of nuclear materials , volume=. 1992 , publisher=

1992
[130]

Radiation Effects , volume=

The interaction of injected helium with lattice defects in a tungsten crystal , author=. Radiation Effects , volume=. 1972 , publisher=

1972
[131]

Journal of Nuclear Materials , volume=

Trapping and release of helium in tungsten , author=. Journal of Nuclear Materials , volume=. 2011 , publisher=

2011
[132]

Philosophical Magazine , volume=

Simulations of weak-beam diffraction contrast images of dislocation loops by the many-beam Howie--Basinski equations , author=. Philosophical Magazine , volume=. 2006 , publisher=

2006
[133]

Nuclear Fusion , volume=

A multi-scale model for stresses, strains and swelling of reactor components under irradiation , author=. Nuclear Fusion , volume=. 2018 , publisher=

2018
[134]

Physical review letters , volume=

Competing kinetics and He bubble morphology in W , author=. Physical review letters , volume=. 2015 , publisher=

2015
[135]

Scientific reports , volume=

Non-contact measurement of thermal diffusivity in ion-implanted nuclear materials , author=. Scientific reports , volume=. 2015 , publisher=

2015
[136]

Journal of nuclear materials , volume=

Deformation microstructure of neutron-irradiated pure polycrystalline vanadium , author=. Journal of nuclear materials , volume=. 2005 , publisher=

2005
[137]

Applied Physics Letters , volume=

Orientation-dependent indentation response of helium-implanted tungsten , author=. Applied Physics Letters , volume=. 2019 , publisher=

2019
[138]

Physica scripta , volume=

Modelling radiation damage and He production in tungsten , author=. Physica scripta , volume=
[139]

Journal of nuclear materials , volume=

Energy spectra of primary knock-on atoms under neutron irradiation , author=. Journal of nuclear materials , volume=. 2015 , publisher=

2015
[140]

Journal of Nuclear Materials , volume=

Radiation damage production in massive cascades initiated by fusion neutrons in tungsten , author=. Journal of Nuclear Materials , volume=. 2014 , publisher=

2014
[141]

Materials Research Letters , volume=

Cascade fragmentation: deviation from power law in primary radiation damage , author=. Materials Research Letters , volume=. 2017 , publisher=

2017
[142]

Acta Materialia , volume=

Direct observation of the spatial distribution of primary cascade damage in tungsten , author=. Acta Materialia , volume=. 2018 , publisher=

2018
[143]

Ultramicroscopy , volume=

3D reconstruction of the spatial distribution of dislocation loops using an automated stereo-imaging approach , author=. Ultramicroscopy , volume=. 2018 , publisher=

2018
[144]

Europhysics Letters , volume=

High-energy collision cascades in tungsten: Dislocation loops structure and clustering scaling laws , author=. Europhysics Letters , volume=. 2013 , publisher=

2013
[145]

Journal of Nuclear Materials , volume=

Defect structures and statistics in overlapping cascade damage in fusion-relevant bcc metals , author=. Journal of Nuclear Materials , volume=. 2018 , publisher=

2018
[146]

Journal of nuclear materials , volume=

Diffraction imaging and diffuse scattering by small dislocation loops , author=. Journal of nuclear materials , volume=. 2007 , publisher=

2007
[147]

Scientific reports , volume=

3D lattice distortions and defect structures in ion-implanted nano-crystals , author=. Scientific reports , volume=. 2017 , publisher=

2017
[148]

Journal of nuclear materials , volume=

Phase diagram and lattice instability in tungsten--rhenium alloys , author=. Journal of nuclear materials , volume=. 2000 , publisher=

2000
[149]

Journal of Physics: Condensed Matter , volume=

Radiation-induced strengthening and absorption of dislocation loops in ferritic Fe--Cr alloys: the role of Cr segregation , author=. Journal of Physics: Condensed Matter , volume=. 2013 , publisher=

2013
[150]

Philosophical Magazine , volume=

A model for the dynamics of loop drag by a gliding dislocation , author=. Philosophical Magazine , volume=. 2005 , publisher=

2005
[151]

Tungsten , volume=

Interaction of edge dislocations with voids in tungsten , author=. Tungsten , volume=. 2024 , publisher=

2024
[152]

Journal of Physics: Condensed Matter , volume=

Structure and metastability of mesoscopic vacancy and interstitial loop defects in iron and tungsten , author=. Journal of Physics: Condensed Matter , volume=
[153]

Radiation Effects and Defects in Solids , volume=

Simulation of the interaction between an edge dislocation and <111> interstitial dislocation loops in -iron , author=. Radiation Effects and Defects in Solids , volume=. 2019 , publisher=

2019
[154]

Philosophical Magazine , volume=

Computer simulation of reactions between an edge dislocation and glissile self-interstitial clusters in iron , author=. Philosophical Magazine , volume=. 2006 , publisher=

2006
[155]

Journal of Physics: Condensed Matter , volume=

The effect of temperature and strain rate on the interaction between an edge dislocation and an interstitial dislocation loop in -iron , author=. Journal of Physics: Condensed Matter , volume=
[156]

Scripta Materialia , volume=

Molecular dynamics simulations of the interactions between screw dislocations and self-interstitial clusters in body-centered cubic Fe , author=. Scripta Materialia , volume=. 2008 , publisher=

2008
[157]

Philosophical magazine , volume=

Reactions between a 1/2< 111> screw dislocation and< 100> interstitial dislocation loops in alpha-iron modelled at atomic scale , author=. Philosophical magazine , volume=. 2010 , publisher=

2010
[158]

Acta materialia , volume=

Cr segregation on dislocation loops enhances hardening in ferritic Fe--Cr alloys , author=. Acta materialia , volume=. 2013 , publisher=

2013
[159]

Nuclear Fusion , volume=

Surface modification of tungsten and tungsten--tantalum alloys exposed to high-flux deuterium plasma and its impact on deuterium retention , author=. Nuclear Fusion , volume=. 2013 , publisher=

2013
[160]

Journal of Nuclear Materials , volume=

A description of bubble growth and gas release of helium implanted tungsten , author=. Journal of Nuclear Materials , volume=. 2009 , publisher=

2009
[161]

Journal of Materials Research and Technology , volume=

A critical review on additive manufacturing of Ti-6Al-4V alloy: Microstructure and mechanical properties , author=. Journal of Materials Research and Technology , volume=. 2022 , publisher=

2022
[162]

Advances in Materials and Processing Technologies , volume=

Effect of the lattice structures on mechanical characterisation of additively manufactured Ti-6Al-4V for biomedical application , author=. Advances in Materials and Processing Technologies , volume=. 2025 , publisher=

2025
[163]

Computational Materials Science , volume=

Crystal plasticity finite element modelling of coarse-grained -uranium , author=. Computational Materials Science , volume=. 2020 , publisher=

2020
[164]

Journal of the Mechanics and Physics of Solids , volume=

On the potential of recurrent neural networks for modeling path dependent plasticity , author=. Journal of the Mechanics and Physics of Solids , volume=. 2020 , publisher=

2020
[165]

Computational Materials Science , volume=

DAMASK – The Düsseldorf Advanced Material Simulation Kit for modeling multi-physics crystal plasticity, damage, and thermal behavior , author=. Computational Materials Science , volume=. 2019 , publisher=

2019
[166]

and Wang, D

Diehl, M. and Wang, D. and Liu, C. and Rezaei Mianroodi, J. and Han, F. and Ma, D. and Kok, P. J. J. and Roters, F. and Shanthraj, P. , journal=. Solving material mechanics and multiphysics problems of metals with complex microstructures using DAMASK—The D. 2020 , publisher=

2020
[167]

Advanced Engineering Materials , volume=

Comparative study of room and cryogenic deformation behavior of additive manufactured Ti--6Al--4V alloy , author=. Advanced Engineering Materials , volume=. 2024 , publisher=

2024
[168]

Materials & Design , volume=

Additive manufacturing of Ti6Al4V alloy: A review , author=. Materials & Design , volume=. 2019 , publisher=

2019
[169]

Materials Characterization , volume=

Forescattered electron imaging of nanoparticles in scanning electron microscopy , author=. Materials Characterization , volume=. 2019 , publisher=

2019
[170]

Applied Materials Today , volume=

Additive manufacturing of Titanium alloy for aerospace applications: Insights into the process, microstructure, and mechanical properties , author=. Applied Materials Today , volume=. 2024 , publisher=

2024
[171]

Materials & Design , volume=

Metal additive manufacturing in aerospace: A review , author=. Materials & Design , volume=. 2021 , publisher=

2021
[172]

Science and Technology of Welding and Joining , volume=

Alternative friction stir welding technology for titanium--6Al--4V propellant tanks within the space industry , author=. Science and Technology of Welding and Joining , volume=. 2017 , publisher=

2017
[173]

Nature communications , volume=

Designing against phase and property heterogeneities in additively manufactured titanium alloys , author=. Nature communications , volume=. 2022 , publisher=

2022
[174]

Virtual and Physical Prototyping , volume=

Recent advance in laser powder bed fusion of Ti--6Al--4V alloys: microstructure, mechanical properties and machinability , author=. Virtual and Physical Prototyping , volume=. 2025 , publisher=

2025
[175]

Acta Materialia , volume=

Anisotropic tensile behavior of Ti--6Al--4V components fabricated with directed energy deposition additive manufacturing , author=. Acta Materialia , volume=. 2015 , publisher=

2015
[176]

Materials Characterization , volume=

Process-structure-property considerations for wire-based directed energy deposition of Ti-6Al-4V , author=. Materials Characterization , volume=. 2023 , publisher=

2023
[177]

Acta Materialia , volume=

Additive manufacturing of strong and ductile Ti--6Al--4V by selective laser melting via in situ martensite decomposition , author=. Acta Materialia , volume=. 2015 , publisher=

2015
[178]

Journal of Alloys and Compounds , volume=

Heat treatment of Ti6Al4V produced by Selective Laser Melting: Microstructure and mechanical properties , author=. Journal of Alloys and Compounds , volume=. 2012 , publisher=

2012
[179]

Materials Science and Engineering: A , volume=

Deformation and strength of Ti--6Al--4V alloyed with B at cryogenic temperatures , author=. Materials Science and Engineering: A , volume=. 2014 , publisher=

2014
[180]

Materials Science and Engineering: A , volume=

Deformation twinning in Ti-6Al-4 V during low strain rate deformation to moderate strains at room temperature , author=. Materials Science and Engineering: A , volume=. 2010 , publisher=

2010
[181]

3D: a digital representation environment for the analysis of microstructure in 3D , author=

DREAM. 3D: a digital representation environment for the analysis of microstructure in 3D , author=. Integrating Materials and Manufacturing innovation , volume=. 2014 , publisher=

2014
[182]

3D representative volume elements and DAMASK crystal plasticity simulations: an integrated computational materials engineering approach , author=

Identifying structure--property relationships through DREAM. 3D representative volume elements and DAMASK crystal plasticity simulations: an integrated computational materials engineering approach , author=. Jom , volume=. 2017 , publisher=

2017
[183]

Scientific Reports , volume=

Crystal plasticity simulations with representative volume element of as-build laser powder bed fusion materials , author=. Scientific Reports , volume=. 2023 , publisher=

2023
[184]

Computer Methods in Applied Mechanics and Engineering , volume=

Three dimensional predictions of grain scale plasticity and grain boundaries using crystal plasticity finite element models , author=. Computer Methods in Applied Mechanics and Engineering , volume=. 2014 , publisher=

2014
[185]

International Journal of Plasticity , volume=

Using texture components in crystal plasticity finite element simulations , author=. International Journal of Plasticity , volume=. 2004 , publisher=

2004
[186]

International Journal of Plasticity , volume=

A three-dimensional crystal plasticity model for duplex Ti--6Al--4V , author=. International Journal of Plasticity , volume=. 2007 , publisher=

2007
[187]

Computational Materials Science , volume=

Crystal plasticity simulations of fretting of Ti-6Al-4V in partial slip regime considering effects of texture , author=. Computational Materials Science , volume=. 2008 , publisher=

2008
[188]

International journal of material forming , volume=

Phenomenological and crystal plasticity approaches to describe the mechanical behaviour of Ti6Al4V titanium alloy , author=. International journal of material forming , volume=. 2011 , publisher=

2011
[189]

Computational Materials Science , volume=

A dislocation density based constitutive law for BCC materials in crystal plasticity FEM , author=. Computational Materials Science , volume=. 2007 , publisher=

2007
[190]

Acta Materialia , volume=

A dislocation density based constitutive model for crystal plasticity FEM including geometrically necessary dislocations , author=. Acta Materialia , volume=. 2006 , publisher=

2006
[191]

Advanced Science , volume=

Machine-Learning Microstructure for Inverse Material Design , author=. Advanced Science , volume=. 2021 , publisher=

2021
[192]

International Journal of Plasticity , volume=

Consistent determination of geometrically necessary dislocation density from simulations and experiments , author=. International Journal of Plasticity , volume=. 2018 , publisher=

2018
[193]

Scientific reports , volume=

Hardening and strain localisation in helium-ion-implanted tungsten , author=. Scientific reports , volume=. 2019 , publisher=

2019
[194]

Nature , volume=

Multiscale modelling of plastic flow localization in irradiated materials , author=. Nature , volume=. 2000 , publisher=

2000
[195]

Journal of Materials Research , volume=

Modeling defect cluster evolution in irradiated structural materials: Focus on comparing to high-resolution experimental characterization studies , author=. Journal of Materials Research , volume=. 2015 , publisher=

2015
[196]

Mrs Bulletin , volume=

Multiscale-multiphysics modeling of radiation-damaged materials: embrittlement of pressure-vessel steels , author=. Mrs Bulletin , volume=. 2001 , publisher=

2001
[197]

International Journal of Plasticity , volume=

Modified deformation behaviour of self-ion irradiated tungsten: A combined nano-indentation, HR-EBSD and crystal plasticity study , author=. International Journal of Plasticity , volume=. 2020 , publisher=

2020
[198]

Advanced Engineering Materials , volume=

Uncertainty quantification of microstructures: a perspective on forward and inverse problems for mechanical properties of aerospace materials , author=. Advanced Engineering Materials , volume=. 2025 , publisher=

2025
[199]

Acta Materialia , volume=

Inverse stochastic microstructure design , author=. Acta Materialia , volume=. 2024 , publisher=

2024
[200]

Engineering Fracture Mechanics , volume=

Fatigue-crack propagation and fracture toughness behavior of cast stainless steels , author=. Engineering Fracture Mechanics , volume=. 1988 , publisher=

1988
[201]

Journal of Nuclear Materials , volume=

Fatigue life of helium-implanted AISI 316 L at 500 and 600° C , author=. Journal of Nuclear Materials , volume=. 1988 , publisher=

1988
[202]

Journal of Nuclear Materials , volume=

An assessment of tensile, irradiation creep, creep rupture, and fatigue behavior in austenitic stainless steels with emphasis on spectral effects , author=. Journal of Nuclear Materials , volume=. 1990 , publisher=

1990
[203]

Surface and Coatings Technology , volume=

Ion implantation effects on fatigue properties of Fe-13Cr-15Ni alloys , author=. Surface and Coatings Technology , volume=. 1992 , publisher=

1992
[204]

Journal of Nuclear Materials , volume=

Multiple ion implantation effects on hardness and fatigue properties of Fe 13Cr 15Ni alloys , author=. Journal of Nuclear Materials , volume=. 1992 , publisher=

1992
[205]

Journal of Nuclear Materials , volume=

Fatigue tests on a ferritic-martensitic steel at 420 C: Comparison between in-situ and postirradiation properties , author=. Journal of Nuclear Materials , volume=. 1994 , publisher=

1994
[206]

and Lindau, R

Bertsch, J. and Lindau, R. and M. In-situ and post-irradiation fatigue properties of the ferritic—martensitic steel Manet at T= 250 ^. Journal of nuclear materials , volume=. 1996 , publisher=

1996
[207]

Journal of Materials Engineering and Performance , volume=

Effects of ion irradiation on fatigue of Fe-12Cr-20Mn stainless steel for fusion reactor applications , author=. Journal of Materials Engineering and Performance , volume=. 1997 , publisher=

1997
[208]

and Nagakawa, J

Murase, Y. and Nagakawa, J. and Yamamoto, N. , journal=. Fatigue behavior of 20\. 2002 , publisher=

2002
[209]

and Nagakawa, J

Murase, Y. and Nagakawa, J. and Yamamoto, N. , journal=. Comparison of in-beam fatigue behavior between austenitic and ferritic steels at 60 ^. 2002 , publisher=

2002
[210]

Nuclear Materials and Energy , volume=

Fatigue properties of ferritic/martensitic steel after neutron irradiation and helium implantation , author=. Nuclear Materials and Energy , volume=. 2020 , publisher=

2020
[211]

Materials Science and Engineering: A , pages=

Crystal plasticity model for cyclic hardening-softening of 316L steel produced by laser-powder bed fusion including the role of sub-grain structures , author=. Materials Science and Engineering: A , pages=. 2025 , publisher=

2025
[212]

Acta Materialia , volume=

Simulation of crystal plasticity in irradiated metals: A case study on Zircaloy-4 , author=. Acta Materialia , volume=. 2022 , publisher=

2022
[213]

, author=

Crack growth rates and fracture toughness of irradiated austenitic stainless steels in BWR environments. , author=. 2008 , institution=

2008
[214]

2013 , institution=

Crack growth rate and fracture toughness tests on irradiated cast stainless steels , author=. 2013 , institution=

2013
[215]

Scripta Materialia , volume=

Orientation dependence of the nano-indentation behaviour of pure Tungsten , author=. Scripta Materialia , volume=. 2020 , publisher=

2020
[216]

Materials Science and Engineering: A , pages=

Characterisation of Irradiation Damage in Fe--3Cr and Fe--5Cr: A Study on the Effects of Chromium Content and Temperature , author=. Materials Science and Engineering: A , pages=. 2025 , publisher=

2025
[217]

Acta Materialia , volume=

Characterising ion-irradiated FeCr: hardness, thermal diffusivity and lattice strain , author=. Acta Materialia , volume=. 2020 , publisher=

2020
[218]

Journal of Nuclear Materials , volume=

Irradiation hardening of stainless steel model alloy after Fe-ion irradiation and post-irradiation annealing treatment , author=. Journal of Nuclear Materials , volume=. 2021 , publisher=

2021
[219]

Scientific reports , volume=

Probing nanoscale damage gradients in ion-irradiated metals using spherical nanoindentation , author=. Scientific reports , volume=. 2017 , publisher=

2017
[220]

Fatigue & Fracture of Engineering Materials & Structures , volume=

A review of deformation and fatigue of metals at small size scales , author=. Fatigue & Fracture of Engineering Materials & Structures , volume=. 2005 , publisher=

2005
[221]

Fusion Science and Technology , volume=

Comparative assessment of material performance in demo fusion reactors , author=. Fusion Science and Technology , volume=. 2014 , publisher=

2014
[222]

International Journal of Plasticity , pages=

Crystal Plasticity Modeling of Hardening and Creep in Ferritic-Martensitic Alloys Under Thermal and Irradiation Environments , author=. International Journal of Plasticity , pages=. 2025 , publisher=

2025
[223]

Computational Materials Science , volume=

Sensitivity of local cyclic deformation in lath martensite to flow rule and slip system in crystal plasticity , author=. Computational Materials Science , volume=. 2023 , publisher=

2023
[224]

Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms , volume=

A combined thermomechanical and radiation testing platform for a 6 MV tandem accelerator , author=. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms , volume=. 2021 , publisher=

2021
[225]

Journal of Nuclear Materials , volume=

Tensile and low cycle fatigue properties of EUROFER97-steel after 16.3 dpa neutron irradiation at 523, 623 and 723 K , author=. Journal of Nuclear Materials , volume=. 2013 , publisher=

2013
[226]

Journal of Nuclear Materials , volume=

Effect of helium to dpa ratio on fatigue behavior of austenitic stainless steel irradiated to 2 dpa , author=. Journal of Nuclear Materials , volume=. 2000 , publisher=

2000
[227]

Journal of Nuclear Materials , volume=

The effect of neutron irradiation on the fatigue behaviour of AISI 316L—Results of first in-pile tests , author=. Journal of Nuclear Materials , volume=. 1991 , publisher=

1991
[228]

Journal of Nuclear Materials , volume=

Fatigue properties of F82H irradiated at 523 K to 3.8 dpa , author=. Journal of Nuclear Materials , volume=. 2004 , publisher=

2004
[229]

Nuclear Fusion , volume=

Material testing facilities and programs for plasma-facing component testing , author=. Nuclear Fusion , volume=. 2017 , publisher=

2017
[230]

SN Applied Sciences , volume=

Recent advances in characterising irradiation damage in tungsten for fusion power , author=. SN Applied Sciences , volume=. 2019 , publisher=

2019
[231]

Fusion Engineering and Design , volume=

Thermal-hydraulic analysis of the First Wall of a CO2 cooled pebble bed breeding blanket for the EU-DEMO , author=. Fusion Engineering and Design , volume=. 2019 , publisher=

2019
[232]

Fusion Engineering and Design , volume=

Thermal and structural analysis of JT-60SA actively cooled divertor target submitted to high heat flux , author=. Fusion Engineering and Design , volume=. 2024 , publisher=

2024
[233]

Journal of Nuclear Materials , volume=

Effects of irradiation temperature and dose rate on the mechanical properties of self-ion implanted Fe and Fe--Cr alloys , author=. Journal of Nuclear Materials , volume=. 2013 , publisher=

2013
[234]

Journal of Nuclear Materials , volume=

Microstructure evolution during irradiation , author=. Journal of Nuclear Materials , volume=. 1994 , publisher=

1994
[235]

Scientific reports , volume=

New insights into microstructure of neutron-irradiated tungsten , author=. Scientific reports , volume=. 2021 , publisher=

2021
[236]

Virtual and Physical Prototyping , volume=

A multiscale crystal plasticity-multistage fatigue coupling framework for prediction of low-cycle fatigue life in laser additively manufactured titanium alloy , author=. Virtual and Physical Prototyping , volume=. 2025 , publisher=

2025
[237]

Engineering Fracture Mechanics , volume=

The effects of laser peening treatment on the very high cycle fatigue properties for AA2024-T351 alloy using a crystal plasticity framework , author=. Engineering Fracture Mechanics , volume=. 2022 , publisher=

2022
[238]

Scientific Reports , volume=

A comprehensive study on the impact of He ion irradiation on the microstructure and mechanical properties of a Ni-Cr-Mo alloy , author=. Scientific Reports , volume=. 2025 , publisher=

2025
[239]

Journal of Nuclear Materials , volume=

Microstructural investigation of irradiation damage behavior of proton irradiated Zr-1 wt.\ author=. Journal of Nuclear Materials , volume=. 2020 , publisher=

2020
[240]

International Journal of Fatigue , volume=

Synergistic effect of microstructure and defects on the initiation of fatigue cracks in additively manufactured Inconel 718 , author=. International Journal of Fatigue , volume=. 2022 , publisher=

2022
[241]

Nuclear Fusion , volume=

ITER materials irradiation within the D--T neutron environment at JET: post-irradiation radioactivity analysis following the DTE2 experimental campaign , author=. Nuclear Fusion , volume=. 2024 , publisher=

2024
[242]

Journal of Nuclear Materials , volume=

Further development of large-scale atomistic modelling techniques for Fe--Cr alloys , author=. Journal of Nuclear Materials , volume=. 2011 , publisher=

2011
[243]

Nuclear fusion , volume=

Radiation damage in ferritic/martensitic steels for fusion reactors: a simulation point of view , author=. Nuclear fusion , volume=. 2007 , publisher=

2007
[244]

Journal of Nuclear Materials , volume=

Evolution of vacancy defects in heavy ion irradiated tungsten exposed to helium plasma , author=. Journal of Nuclear Materials , volume=. 2020 , publisher=

2020
[245]

Nuclear Fusion , volume=

Clustering of transmutation elements tantalum, rhenium and osmium in tungsten in a fusion environment , author=. Nuclear Fusion , volume=. 2017 , publisher=

2017
[246]

Physica B: Condensed Matter , volume=

Radiation damage studies in fusion reactor steels by means of small-angle neutron scattering (SANS) , author=. Physica B: Condensed Matter , volume=. 2018 , publisher=

2018
[247]

Nuclear Materials and Energy , volume=

Proton and Au-ion irradiation induced damage and hardening in ferritic/martensitic steel , author=. Nuclear Materials and Energy , volume=. 2021 , publisher=

2021
[248]

Plasma Physics and Controlled Fusion , volume=

Characteristics of type I ELM energy and particle losses in existing devices and their extrapolation to ITER , author=. Plasma Physics and Controlled Fusion , volume=. 2003 , publisher=

2003
[249]

Matter and Radiation at Extremes , volume=

Challenges for plasma-facing components in nuclear fusion , author=. Matter and Radiation at Extremes , volume=. 2019 , publisher=

2019
[250]

Nature , volume=

Ion implantation , author=. Nature , volume=. 1975 , publisher=

1975
[251]

Nuclear Fusion , volume=

The influence of Fe-ion irradiation on the microstructure of reduced activation ferritic-martensitic steel Eurofer 97 , author=. Nuclear Fusion , volume=. 2019 , publisher=

2019
[252]

Proc Indian Natn Sci Acad , volume=

Materials research and development opportunities in fusion reactors , author=. Proc Indian Natn Sci Acad , volume=
[253]

Structural Alloys for Nuclear Energy Applications , pages=

Overview of reactor systems and operational environments for structural materials in fusion reactors , author=. Structural Alloys for Nuclear Energy Applications , pages=. 2019 , publisher=

2019
[254]

Nuclear Materials and Energy , volume=

Multiphysics optimization for first wall design enhancement in water-cooled breeding blankets , author=. Nuclear Materials and Energy , volume=. 2021 , publisher=

2021
[255]

Materials , volume=

Materials to be used in future magnetic confinement fusion reactors: a review , author=. Materials , volume=. 2022 , publisher=

2022
[256]

Journal of Nuclear Materials , volume=

Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure , author=. Journal of Nuclear Materials , volume=. 2000 , publisher=

2000
[257]

2020 , institution=

Cavity swelling in irradiated materials , author=. 2020 , institution=

2020
[258]

Nuclear Fusion , volume=

Towards a programme of testing and qualification for structural and plasma-facing materials in ‘fusion neutron’environments , author=. Nuclear Fusion , volume=. 2017 , publisher=

2017
[259]

Nuclear Fusion , volume=

A staged approach to Indian DEMO , author=. Nuclear Fusion , volume=. 2023 , publisher=

2023
[260]

Fusion Engineering and Design , volume=

Strategy for the Indian DEMO design , author=. Fusion Engineering and Design , volume=. 2008 , publisher=

2008
[261]

Nuclear Fusion , volume=

Overview of physics results from the ADITYA-U tokamak and future experiments , author=. Nuclear Fusion , volume=. 2024 , publisher=

2024
[262]

International Journal of Fatigue , volume=

Crystal plasticity FEM study of material and mechanical effects on damage accumulation mode of fatigue crack propagation , author=. International Journal of Fatigue , volume=. 2023 , publisher=

2023
[263]

Fusion Science and Technology , volume=

Reduced activation ferritic martensitic steel and fabrication technologies for the Indian test blanket module in ITER , author=. Fusion Science and Technology , volume=. 2014 , publisher=

2014
[264]

Journal of Nuclear Materials , volume=

Development of India-specific RAFM steel through optimization of tungsten and tantalum contents for better combination of impact, tensile, low cycle fatigue and creep properties , author=. Journal of Nuclear Materials , volume=. 2013 , publisher=

2013
[265]

Fusion Engineering and Design , volume=

Development of IN-RAFM steel and fabrication technologies for Indian TBM , author=. Fusion Engineering and Design , volume=. 2016 , publisher=

2016
[266]

Journal of Nuclear Materials , volume=

Emulation of neutron irradiation effects with protons: validation of principle , author=. Journal of Nuclear Materials , volume=. 2002 , publisher=

2002
[267]

Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms , volume=

SRIM--The stopping and range of ions in matter (2010) , author=. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms , volume=. 2010 , publisher=

2010
[268]

Encyclopedia of Materials: Science and Technology , publisher =

Ion Implantation , editor =. Encyclopedia of Materials: Science and Technology , publisher =. 2001 , author =

2001
[269]

Computer Physics Communications , volume=

Atomsk: A tool for manipulating and converting atomic data files , author=. Computer Physics Communications , volume=. 2015 , publisher=

2015
[270]

Modelling and simulation in materials science and engineering , volume=

Visualization and analysis of atomistic simulation data with OVITO--the Open Visualization Tool , author=. Modelling and simulation in materials science and engineering , volume=
[271]

Journal of Nuclear Materials , volume=

Dislocation pinning in helium-implanted tungsten: A molecular dynamics study , author=. Journal of Nuclear Materials , volume=. 2024 , publisher=

2024
[272]

Acta Materialia , volume=

Simulation of the interaction between an edge dislocation and a< 1 0 0> interstitial dislocation loop in -iron , author=. Acta Materialia , volume=. 2008 , publisher=

2008
[273]

International Journal of Plasticity , volume=

Atomistic investigation of the interaction between an edge dislocation and 1/2< 111> interstitial dislocation loops in irradiated tungsten , author=. International Journal of Plasticity , volume=. 2024 , publisher=

2024
[274]

Acta Materialia , volume=

Characterisation of radiation damage in W and W-based alloys from 2 MeV self-ion near-bulk implantations , author=. Acta Materialia , volume=. 2015 , publisher=

2015
[275]

Europhysics Letters , volume=

Direct observation of size scaling and elastic interaction between nano-scale defects in collision cascades , author=. Europhysics Letters , volume=. 2015 , publisher=

2015
[276]

Nature materials , volume=

Multiscale modelling of defect kinetics in irradiated iron , author=. Nature materials , volume=. 2005 , publisher=

2005
[277]

Micron , volume=

Three-dimensional scanning transmission electron microscopy of dislocation loops in tungsten , author=. Micron , volume=. 2018 , publisher=

2018
[278]

npj Computational Materials , volume=

Learning dislocation dynamics mobility laws from large-scale MD simulations , author=. npj Computational Materials , volume=. 2024 , publisher=

2024
[279]

Scripta Materialia , volume=

A molecular dynamics-informed probabilistic cross-slip model in discrete dislocation dynamics , author=. Scripta Materialia , volume=. 2021 , publisher=

2021
[280]

Journal of the Mechanics and Physics of Solids , volume=

Atomistically informed dislocation dynamics in fcc crystals , author=. Journal of the Mechanics and Physics of Solids , volume=. 2008 , publisher=

2008
[281]

Journal of Micromechanics and Molecular Physics , volume=

Dislocation dynamics in polycrystals with atomistic-informed mechanisms of dislocation-grain boundary interactions , author=. Journal of Micromechanics and Molecular Physics , volume=. 2017 , publisher=

2017
[282]

Journal of the Mechanics and Physics of Solids , volume=

The coupled atomistic/discrete-dislocation method in 3d part I: Concept and algorithms , author=. Journal of the Mechanics and Physics of Solids , volume=. 2018 , publisher=

2018
[283]

Journal of the Mechanics and Physics of Solids , volume=

Coupled atomistic/discrete dislocation method in 3D Part II: Validation of the method , author=. Journal of the Mechanics and Physics of Solids , volume=. 2018 , publisher=

2018
[284]

Part III: dynamics of hybrid dislocations , author=

The coupled atomistic/discrete-dislocation method in 3d. Part III: dynamics of hybrid dislocations , author=. Journal of the Mechanics and Physics of Solids , volume=. 2018 , publisher=

2018
[285]

Journal of Physics: Condensed Matter , volume=

On the binding of nanometric hydrogen--helium clusters in tungsten , author=. Journal of Physics: Condensed Matter , volume=. 2014 , publisher=

2014

Pith tools

Reviewed August 1, 2026 · model on record in the stance chip above.

[1] [1]

Acta Materialia , volume=

Atomistic insights into the enhancement of dynamic yield and fracture responses by chemical short-range order in CoCrNi multi-principal element alloy under quasi-isentropic loading , author=. Acta Materialia , volume=. 2026 , publisher=

2026

[2] [2]

International Journal of Plasticity , volume=

Experiments and/or crystal plasticity finite element modeling of the mechanical properties of pristine and irradiated tungsten single crystal , author=. International Journal of Plasticity , volume=. 2022 , publisher=

2022

[3] [3]

International Journal of Plasticity , volume=

Temperature dependent deformation localization in irradiated tungsten , author=. International Journal of Plasticity , volume=. 2021 , publisher=

2021

[4] [4]

International Journal of Plasticity , volume=

Atomic irradiation defects induced hardening model in irradiated tungsten based on molecular dynamics and CPFEM , author=. International Journal of Plasticity , volume=. 2024 , publisher=

2024

[5] [5]

International Journal of Plasticity , volume=

Dislocation motion in tungsten: atomistic input to discrete dislocation simulations , author=. International Journal of Plasticity , volume=. 2013 , publisher=

2013

[6] [6]

Acta Materialia , volume=

A phenomenological dislocation mobility law for bcc metals , author=. Acta Materialia , volume=. 2016 , publisher=

2016

[7] [7]

Nature Communications , volume=

Repulsion leads to coupled dislocation motion and extended work hardening in bcc metals , author=. Nature Communications , volume=. 2020 , publisher=

2020

[8] [8]

Materials Science and Engineering: A , volume=

A mechanism-based quantitative multi-scale framework for investigating irradiation hardening of tungsten at low temperature , author=. Materials Science and Engineering: A , volume=. 2020 , publisher=

2020