PHYSICAL REVIEW B 84, 104109 (2011)
Radiation-induced damage and evolution of defects in Mo
Sergey V. Starikov,* Zeke Insepov,† and Jeffrey Rest
Argonne National Laboratory, Argonne, Illinois 60439, USA
Alexey Yu. Kuksin, Genri E. Norman, Vladimir V. Stegailov, and
Alexey V. Yanilkin
Joint Institute for High Temperatures, Russian Academy of Sciences, Moscow 125412, Russia and
Moscow Institute of Physics and Technology, Dolgoprudny 141700, Russia
(Received 30 December 2010; revised manuscript received 13 May 2011; published 8 September 2011)
The formation of defects in bcc Mo lattice as a result of 50-keV Xe bombardment is studied via atomistic
simulation with an interatomic potential developed using the force-matching ab initio based approach. The
defect evolution in the cascade is described. Diffusion and interaction of interstitials and vacancies are analyzed.
Only small interstitial atom clusters form directly in the cascade. Larger clusters grow only via aggregation at
temperatures up to 2000 K. Stable forms of clusters demonstrate one-dimensional diffusion with a very high
diffusion coefficient and escape quickly to the open surface. Point vacancies have much lower diffusivity and
do not aggregate. The possibility of a large prismatic vacancy loop formation near the impact surface as a result
of fast recrystallization is revealed. The mobility of the vacancy dislocation loop segments is high, however, the
motion of the entire loops is strongly hindered by neighbor point defects. This paper explains the existence of
the large prismatic vacancy loops and the absence of the interstitial loops in the recent experiments with ion
irradiation of Mo foils.
DOI: 10.1103/PhysRevB.84.104109
PACS number(s): 61.80.−x, 64.30.−t, 64.70.D−, 71.10.Li
I. INTRODUCTION
The strength and mechanical properties of nuclear fuel
pellets as well as structural materials of nuclear reactors essentially depend on the influence of neutron irradiation and the
corresponding evolution of the material microstructure. The
evolution of radiation defects is experimentally studied using
transmission electron microscopy in the samples subjected to
neutron irradiation or heavy-ion bombardment.1–8 The method
of heavy-ion implantation mimics the primary knock-on atoms
(PKA) produced by collisions with neutrons. This method
provides more control of the irradiation conditions. However,
the penetration depth of ions is smaller in comparison
with neutrons, and the ion cascades start near the ion-entry
surface (the influence of surfaces is especially pronounced in
experiments with thin foils, e.g., see Ref. 8). The detailed
knowledge of the ion cascade evolution is crucial for the
application of the heavy-ion implantation data for neutron
irradiation conditions.
Although many features of the radiation damage have been
explained, several phenomena are still discussed, including
the mechanisms of production of large clusters of defects
and dislocation loops,5,8–12 the effect of PKA mass on the
defect yield,8,12 the influence of surfaces in the experiments
with thin foils,8 the mobility of self-interstitial atoms (SIAs),
clusters (SIACs), and dislocation loops.2,4,13–16 One of the
most plausible explanations of the formation of superlattices
of bubbles1–3,13,14,16 in several metals under the radiation
damage is based on the anisotropic diffusion of SIAs or
SIACs. However, there are contradicting statements in the
previous works about the mechanisms and dimensionality of
di-interstitial SIA (di-SIA) and SIAC diffusion.2,13,14,16,17 At
the same time, the comparison with the recent experimental
results showed a large discrepancy in the diffusivity of
dislocation loops.4
1098-0121/2011/84(10)/104109(8)
The understanding of the mechanisms of the production of
large clusters of defects is of practical importance for reducing
the irradiation embrittlement. The presence of impurity atoms
and defect sinks can substantially influence the processes of
the radiation softening or hardening if the sessile clusters are
formed via diffusion-controlled nucleation and growth that
has been confirmed for some metals (Ni, Cu, Ag, Pt, and
W). However, the formation mechanism of SIACs in Al, Fe,
and Mo remains still unclear. In the case of the in-cascade
formation of clusters, the influence of impurities is not clear.18
Recent experiments on low-dose (<1016 ions/m2 ) irradiation of Mo single-crystal foils revealed the formation
of vacancy loops within individual cascades by a process
of cascade collapse.8 In iron, under self-ion irradiation, the
cascade collapse is not observed at low doses,6 while visible
damage is seen at high ion doses when cascade overlap
becomes significant as well as in the cascades initiated by
more massive ions.7 For both Mo and Fe, it was shown that the
number of visible loops increases as the mass of the incident
ion becomes larger,6–8 e.g., in the case of molecular ion
irradiation. Dislocation loops mostly composed of vacancies
are observed. Interstitial loops have high mobility, and they
are believed to go to the surfaces and disappear.
A useful tool for studying damage of materials
at high-energy deposition,15,19–23 including displacement
cascades,10–12,18,24–30 is a classical molecular dynamics (MD)
method. A large amount of the displacement cascades
simulations for bcc metals was done on the example of
Fe.10–12,18,24,25,27–29 Cascades in Mo were studied in Ref. 26.
Most of the MD results on radiation damage were obtained
within the PKA model, and the influence of the surface
attracted less attention.30
Both classical MD and electron density functional theory
(DFT) atomistic models were applied to analyze the migration
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PHYSICAL REVIEW B 84, 104109 (2011)
SERGEY V. STARIKOV et al.
mechanisms of defects and to evaluate their mobility (e.g., see
Refs. 15, 31, and 32,). The resulting data can be deployed as
an input for the theoretical models of long time evolution
of damaged material.3,14,33,34 It was shown that both the
SIAs and the vacancy loops have high one-dimensional
(1D) mobility along close-packed crystal directions in bcc
crystals.10,31,32 The small clusters can switch their propagation
direction between equivalent directions, which result in the
three-dimensional (3D) diffusion at elevated temperatures.
While the influence of the interatomic potential in classical
MD cascade models is still not quite clear,11,25 it is concluded
that the number and sizes of vacancy clusters produced during
cascade collapse in Fe under self-ion irradiation are small in
a qualitative agreement with experimental observations. The
increase of the PKA mass results in formation of large SIA and
vacancy clusters or loops,12,29 which are potentially resolvable
by the transmission electron microscopy. However, a certain
disagreement exists. Most loops observed in the thin-foil
experiments are composed of vacancies.7 This peculiarity is
more pronounced for Mo.8 It can be only partially attributed
to the fast glide of SIA loops to the open surfaces8 since the
foils with the 110 surface should preserve a certain fraction
of SIA loops with a glide cylinder aligned in the foil plane.
The defect evolution described above is studied in this work
for the molybdenum single crystal. Mo is a refractory metal
with high strength, radiation, and creep resistance at high
temperatures. The study of radiation damage in pure Mo can
shed light on the mechanical properties of nuclear fuel based
on U-Mo alloys. Basic properties (such as formation energies
and structure) of SIAs in Mo were studied using DFT.31,32 It
was found that the difference in formation energies of 111
crowdion and dumbbell configurations is negligibly small,
which implies the high SIA mobility along the 111 direction
at low temperatures in agreement with the resistivity recovery
experiments.35 The old generation interatomic potentials for
Mo26,36 do not reproduce correctly the hierarchy of formation
energies of SIAs that results in the absence of 1D diffusion
and very small SIA diffusivity at low temperatures. The
potential proposed in Ref. 37 takes into account this hierarchy
but predicts anomalous thermal expansion and gives a large
overestimation of the melting temperature.
In this paper, we construct an interatomic potential for
Mo that correctly describes thermodynamic properties and
energies of the main defect structures and apply this potential
to the radiation cascade studies. The interatomic potential and
the procedure of its construction are described in the Sec. II.
Section III reviews the details of the cascade simulations.
Section IV is devoted to the processes of defect interaction. In
Sec. V, the formation of vacancy loops near the open surface
is discussed.
II. INTERATOMIC POTENTIAL
Here, we develop an embedded-atom method38 (EAM)
interatomic potential for the Mo-Xe system,39 which describes
energetic properties of point defects and defect clusters in
consistency with DFT calculations. The energy Ui of an atom
i is given by
Ui = Fα (ρ i ) +
ϕ αβ (rij ),ρi =
ρβ (rij ),
(1)
j =i
j =i
where F is the embedding energy that is a function of the
electron density ρ, ϕ is a pair potential interaction, and α
and β are the element types of atoms i and j . The multibody
nature of the EAM potential is a result of the embedding energy
term. Both summations in the formula are over all neighbors
j of atom i within the cutoff distance. All the functions are
represented as cubic splines with 10 nodes each.
The force-matching method40,41 is used for the development
of the potential as implemented in the POTFIT code.41 This
method provides a way to construct physically justified
interatomic potentials excluding the experimental data from
the fitting database. The idea is to adjust the interatomic
potential functions to optimally reproduce per-atom forces
(together with total energies and stresses) computed at the
ab initio level for a fine-tuned set of reference structures.
The reference data are calculated using the DFT code
VASP (Ref. 42) with approximatly 200 atoms in the supercell
(the number of atoms depends on the strcture, the number
of defects, etc.) The projector augmented-wave (PAW) pseudopotentials together with the plane-wave basis cutoff energy
of 400 eV are used. The Brillouin zone is sampled with the
2 × 2 × 2 Monkhorst-Pack k-point mesh. The generalizedgradient approximation (GGA) of Perdew and Wang43 is used
for the exchange-correlation functional.
We use 81 configurations with 10 746 atoms all together.
These configurations represent 39 states with pure Mo (liquid
and bcc solid at different densities; lattice with SIAs and/or
FIG. 1. (Color online) The functions of the EAM potential for the Mo-Xe system. Pair potentials: (a) solid red line, the Mo-Mo interaction;
black dashed-dotted line, the Mo-Xe interaction; blue short dashed line, the Xe-Xe interaction. Electron densities (b) and embedding functions
(c): solid red line, Mo; blue dashed line, Xe.
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RADIATION-INDUCED DAMAGE AND EVOLUTION OF . . .
TABLE I. The comparison of EAM interatomic potentials of molybdenum at room temperature using the cohesive energy Ec , the equilibrium
lattice parameter a, the elastic constants Cij , and the melting temperature Tm . The experimental data are taken from Refs. 46, 47, and 52.
Ec (eV)
a (Å)
C11 (GPa)
C12 (GPa)
Tm (K)
Experiment
EAM (Ref. 36)
EAM (Ref. 37)
EAM (this work)
6.82
3.1472
465
176
2890
6.85
3.1471
420
170
6.84
3.1465
600
169
3350
6.88
3.1470
550
220
2630
vacancies and/or surface), 20 states with pure Xe (liquid
and solid), and 22 states with Mo and Xe (including a
single Xe atom in pure Mo). The energies and stresses for
different configurations of point defects are included into
the target function with higher weights. Initially, all the
atomic configurations are taken from classical MD runs at
different temperatures performed with some preliminary EAM
potential. The fitting procedure consists of the following steps:
(1) fitting the parameters of the potential to the ab initio
database, (2) testing the potential with respect to certain
properties, and (3) recalculating the initial set of configurations
with the updated potential. This procedure is performed in an
iterative manner in order to improve the description of the
desired properties.
The developed potential reproduces energies, stresses, and
per-atom forces of the reference data with the average accuracy
0.5%, 4%, and 25%, respectively. The potential functions are
shown in Fig. 1. For simulations of high-energy collisions, the
pair parts of the EAM potential are modified at small distances
to transform smoothly into the universal screened Coulomb
potential.44
The basic properties of pure molybdenum calculated with
this and two previously published EAM potentials are summarized in Table I and compared with the experimental data.
The accuracy of the potential is slightly lower than that of its
predecessors at room temperature and zero pressure. However,
this potential has significant advantage in the description of
processes in a wide range of pressures and temperatures. This
EAM potential reproduces the room-temperature isotherms of
Mo and Xe up to approximately 600 GPa in agreement with the
experimental data.45,46 As shown in Fig. 2, the developed potential reproduces the isothermal compression of pure Mo with
good precision. Thermal expansion at zero pressure is reproduced well47 up to the melting point with 1%–2% accuracy as
shown in Fig. 3. Such a behavior is required when temperature
dependencies of certain physical properties are studied.
The melting of pure molybdenum is investigated using twophase simulation.19,48,49 The calculated melting line of pure
Mo is very close to the DFT results of Ref. 50 and agrees well
with the shock-wave test data.51 Figure 4 shows the melting
temperatures Tm at various pressures P . There is a considerable
scatter in the experimental results obtained using the diamond
anvil cell and shock-wave techniques. The possible reasons
for this discrepancy for molybdenum and other metals were
discussed in Refs. 19, 50, and 52–54.
Relative energies of point-defect configurations and clusters
are important for the proper description of their diffusion
mechanisms. One can judge about the stability of defects by
their formation energy
FIG. 2. (Color online) The isotherm of Mo at room temperature:
1, experimental data (Ref. 46); 2, 3 and 4, EAM data for Refs. 37
and 36 and the potential developed in this work, respectively.
FIG. 3. (Color online) The thermal expansion of Mo at zero
pressure: 1, experimental data (Ref. 47); 2, 3 and 4, EAM data for
Refs. 37 and 36 and the potential developed in this work, respectively.
Ef = Edef (N) −
N
Eid (Nid ).
Nid
(2)
Here, Edef is the energy of the system with defect comprising N Mo atoms, and Eid is the total energy of an ideal
lattice with Nid atoms. In order to minimize the energy of the
system, the relaxation of the atomic positions is performed via
the conjugate gradient algorithm. The size of the box is large
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FIG. 4. (Color online) The melting line of Mo: 1, the melting
points obtained in diamond anvil cells (Ref. 52); 2, the melting point
obtained in shock-wave experiment (Ref. 51); 3 and 4, the calculated
melting lines from Refs. 50 and 53; 5, two-phase MD simulation with
the potential developed in this work.
enough (Nid = 250) and the elastic energy due to the defect is
negligible.
This potential gives the following formation energies of
Mo SIAs in different configurations: crowdion 111, 6.42 eV
(C111 ); dumbbell 111, 6.43 eV (D111 ); dumbbell 110, 6.67
eV (D110 ); tetrahedral, 7.19 eV (T ); dumbbell 100, 7.35 eV
(D100 ); and octahedral, 7.77 eV (O). The vacancy formation
energy is 2.79 eV. The relative formation energies of SIA (with
respect to a minimum value) are shown in Fig. 5 in comparison
with the data from DFT and other EAM potentials. The most
stable configurations of SIA are a dumbbell 111 and a
crowdion 111 with very small difference in formation energies, in accordance with DFT calculations.31,32 Such a small
difference between configurations results in a 1D diffusion of
SIA at very low temperatures in agreement with the resistivity
recovery measurements following electron irradiation.35 The
1D diffusion proceeds via sequential transformations of SIA
from crowdion to dumbbell configurations along the 111
axis. The corresponding SIA diffusivity is high: ∼10−4 cm2 /s
at temperatures T 300 K.
FIG. 5. (Color online) The relative formation energy of SIA
(relative to the minimum value): 1 and 2, DFT calculations in Refs. 31
and 32; 3, 4, and 5, EAM data (minimization) for the potentials
from Refs. 37 and 36 and for the potential developed in this work,
respectively.
FIG. 6. (Color online) The types of di-SIA in Mo: (a) stable
mobile type; (b), (c) instable immobile types. The used signs: black
solid squares, atoms of the lattice; red circles, interstitial atoms; open
square, a missing atom of the lattice.
As temperature increases, the 111-110 dumbbell transitions are activated providing rotations of crowdion propagation
directions. The height of the corresponding barrier can be
estimated as a difference in formation energies of the 111
and 110 dumbbells. Such events are quite frequent on the
nanosecond time scale already at 500 K. The dumbbell pair
can change its orientation to any of the four equivalent 111
axes. It provides a viable mechanism for 3D SIA diffusion.
The average length of 1D segments (the distance between
subsequent reorientations) approaches interatomic distances
at T ∼ 2000 K.
This potential is tested by the reproduction of formation
energies of di-SIAs in Mo. Atomic structures of the basic
types of di-SIA are shown in Fig. 6. The formation energies
of di-SIAs are computed by energy minimization in DFT
and MD calculations with this potential. N = 252 atoms are
used in both types of calculations. The results are shown in
Table II. This potential reproduces correctly the di-SIA energy
hierarchy. The more stable type (a) is characterized by 1D
diffusion similar to a single SIA. Note that the metastable types
of di-SIA (b and c) may exist at low temperatures because of
the nonzero energy barrier between them.
The formation energies of the Xe inclusion at different
positions in Mo lattice are shown in Table III. The lowestenergy type of atom arrangement is the substitutional Xe.
It is even favorable for a Xe atom to replace a host Mo
atom, thus producing a SIA. A transition of a Xe atom to an
interstitial position (either octahedral or tetrahedral) requires
considerable energy for activation.
This potential may be useful for the simulation of Xe atoms
evolution in the Mo matrix (e.g., the bubble formation process)
as well as for the simulation in pure Mo. In this work, we
study the evolution of Mo structure under high-energy Xe
bombardment.
III. DETAILS OF CASCADE SIMULATIONS
The evolution of radiation damage in displacement cascades
generated by a single Xe ion in a Mo lattice is studied using
MD simulations. The ion energy is taken to be 48.5 keV. It
is assumed that there is no difference between the surface
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RADIATION-INDUCED DAMAGE AND EVOLUTION OF . . .
TABLE II. The calculated formation energies of di-SIAs (the absolute value and the relative value with respect to the SIA doubled energy).
The types of di-SIAs are shown in Fig. 6.
Ef (DFT) (eV)
Ef (EAM) (eV)
Type a
Type b
Type c
Doubled energy of SIA
12.42 (−1.36)
11.71 (−1.12)
12.90 (−0.88)
11.92 (−0.91)
13.53 (−0.25)
12.46 (−0.37)
13.78
12.83
bombardment by a Xe atom or a Xe+ ion at such high kinetic
energy. The x axis is normal to the impact surface. Periodic
boundary conditions are used only in the y and z directions.
Two different crystal orientations of the impact surface are
considered, {100} and {110}, with the latter chosen in order to
provide some of the equivalent 111 glide directions parallel
to a free surface. The ion impact direction is about 6◦ offnormal to the open surface. The simulation box varies in size
from 30 to 80 lattice constants a in the y and z directions and
from 80a to 300a along the x axis. The initial temperature
of the target is 250–2500 K. 50 cascades are calculated and
analyzed in total. MD runs are carried out by the LAMMPS
code.55 The time step is adjusted during the simulation in order
to fulfill the criterion of the maximum allowed displacement
of atom.
During the penetration of a Xe ion into the bulk crystal, the
generation of several subcascades takes place. The penetration
depth varies significantly from one run to another with
the average value of 15 nm. The energy deposited in the
subcascades leads to local disordering within several tenths
of picoseconds followed by recrystallization. This cascade
collapse leads to the formation of vacancies close to the
initiating Xe ion trajectory and SIAs on the periphery. A
single Xe ion cascade produces ∼102 SIAs and vacancies
with smaller numbers at higher T . However, most defects
recombine after 1–2 ps. Single vacancies are practically
immobile in all the temperature ranges considered (even
on the ns time scale). 0.5–1.0 ns after the SIA vacancies
recombination, the interaction of moving defects leads to the
formation of mobile and sessile SIACs (Figs. 7, 8, and 9).
IV. DEFECT INTERACTION IN THE CASCADES
We distinguish the following features of the defect interaction process:
(i) The SIACs produced directly in the cascade are quite
small (2–4 SIAs). A possibility of formation of larger SIA
clusters was reported in previous cascade simulations in Mo,26
however, their average size is also quite small. The growth of
larger clusters (up to 6–7 SIAs) takes place on the nanosecond
time scale as a result of SIA diffusion toward each other.
Therefore, large SIACs in Mo are produced only via diffusion
and coalescence of SIAs. It is consistent with the experimental
evidences obtained for neutron-irradiated Mo,5 where the
influence of the surfaces is small and formation of vacancy
loops on the surfaces (as discussed below) is neglible.
(ii) A SIAC is more stable than separate SIAs. Static
calculations show that the bonding energy of the cluster
increases with cluster size (like in iron10 ). Therefore, at the
collision of two SIAs (or SIA and SIAC), aggregation takes
place. The clusters are formed up to T ∼ 2000 K.
(iii) Stable forms of SIACs show 1D thermal diffusion (the
corresponding diffusion coefficient is of the same order of
magnitude as for single SIAs). The most stable form of SIAC
corresponds to a bundle of crowdions aligned along the 111
direction see Figs. 7(b), 8(c), and Ref. 56, thus retaining 1D
migration (see Ref. 57). Such clusters can be regarded as
nuclei of 111 prismatic dislocation loops. The 1D diffusion
of dislocation loops has been experimentally observed in iron.4
(iv) At T 1000 K, there exists the possibility of formation
of stable immobile SIACs [Figs. 8(a) and 8(b)]. However,
they are less stable than mobile SIACs of the same size, and
relaxation to mobile structures [Figs. 8(b) and 8(c)] is observed
on the ps or ns time scale depending on temperature. This fact
can be explained by the existence of an energy barrier between
mobile and immobile forms of SIACs. At T 1000 K, only
a small amount of immobile SIACs are present. The only
possibility for the formation of immobile SIACs at high
temperatures is from collisions of large mobile SIACs. The
presence of immobile defect clusters at low temperatures
agrees with the results for iron.15
(v) Some part of mobile SIAs and clusters migrate to the
crystal surface and leave the lattice. An excess concentration of
vacancies arises on the ns time scale. In general, the formation
of mobile or immobile SIACs from SIAs is equally probable,
but at T 1000 K, an immobile SIAC quickly relaxes to
mobile structure and can leave the system if its propagation
direction is favorable. The number of lost defects is several
times smaller for the {110} than for {100} open surface.
Therefore, an open surface is an active sink for SIAs and
SIACs at high T .
V. VACANCY LOOPS FORMATION
The formation of a large prismatic vacancy loop is observed
in some runs (approximately in 3 cases out of 50 considered)
TABLE III. The formation energies for the interstitial and substitutional Xe atom in the bcc Mo lattice.
Ef (DFT) (eV)
Ef (EAM) (eV)
Octahedral
Tetrahedral
Substitutional Xe + SIA
Substitutional Xe
17.1
17.1
16.2
16.5
15.8
15.3
8.8
8.4
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FIG. 8. (Color online) Examples of SIACs: (a) an immobile
cluster of 15 SIA; (b) a cluster of 13 SIA initially immobile and (c)
mobile after reorientation of 3 SIAs. (These structures are specially
prepared and not taken from the MD cascade simulations.)
FIG. 7. (Color online) The evolution of a displacement cascade
in Mo produced by a Xe ion. Atoms comprising defects (blue open
circles for vacancies, red solid circles for SIAs) in one half of the
simulation box are shown in xy projection at 5 ps and 3 ns after
the Xe surface impact (T = 1200 K). The inset shows the main SIA
types: (a) a crowdion, (b) 111, and (c) 110 dumbbells. The arrow
shows the path of the Xe ion.
where the displacement cascade produced remains close to the
frontal surface (or sometimes even the rare surface in case of
long cascades) (see Fig. 10). The ion stops in the vicinity of
the crystal surface and its energy is deposited into a relatively
small volume. An intensive expansion of the melt into vacuum
decreases the density of the melt region. Compression of the
disordered region takes place when its temperature decreases.
The recrystallization starts from the bulk at the same time. A
few crystalline layers of atoms can form a hill on the surface
that leads to a large amount of vacancies left in the bulk.
Formation of a prismatic vacancy loop is possible in such
a vacancy-rich region at the last stage of recrystallization.58
Moreover, a number of single vacancies can remain around
this dislocation loop. Similar results were reported in literature
for the Ni3 Al alloy59,60 and discussed hypothetically as an
interpretation of the influence of surfaces on defects production
in experiments.8
Dislocation loops with Burgers vectors 111 are observed
for surfaces of both orientations considered. The image force
due to the open surface results in a loop glide along the 111
direction towards the {100} open surface. Near the {110} open
surface, the vacancy loop stays trapped by the surrounding
point defects within (at least) several hundreds of picoseconds,
while some of its segments exhibit 1D oscillations. Such
an influence of point defects may be the reason for the
difference in the estimates of thermal diffusivity obtained for
the dislocation loops in MD and in experiments.4
One should note a significant difference of the presented
results with a recent MD simulation12 of cascades produced
by Bi ions irradiation of iron (both atomic and molecular): the
formation of large SIA clusters was reported in Ref. 12, which
is not observed in our simulations. The reason is probably
connected with the difference in masses of colliding particles:
a Bi atom is much more massive than a Fe atom, while the
difference between Xe and Mo atoms is smaller. The ratio of
masses in the case of Xe irradiation of the Mo target is very
close to one analyzed in experiments8 where Mo is irradiated
with Sb ions.
The absence of large SIA clusters reported here agrees
well with the experimental observations: only vacancy loops
were reported in Ref. 8. Such observations can be explained
if the vacancy loops are produced in near-surface cascades
via the mechanism described above. Then, the enhanced
production of the loops in case of molecular ion irradiation
(at the same energy per ion) can be connected to the smaller
penetration depth of molecular ions in comparison to a single
ion: molecular ion cascades form closer to the surface and
there is an increased probability of loops formation in a
near-surface vacancy-rich region after fast recrystallization.
FIG. 9. (Color online) The time dependence of interstitial defect concentrations with respect to the initial vacancy concentration for
temperatures (a) 250 K, (b) 800, and (c) 1100 K: 1, SIA; 2, di-interstitial (immobile); 3, di-interstitial (mobile); 4 and 5, clusters with more
than 2 SIAs (immobile and mobile).
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FIG. 10. (Color online) Vacancy loop formation at radiation
damage: (a) t = 5.5 ps; (b) t = 89.3 ps. The solid line is the position
of free surface. Only the disordered atoms (atoms forming defects)
are shown. T = 1100 K. The dark blue (dark gray) particles denote
atoms with low coordination number. The blue/gray and yellow/light
gray particles correspond to high coordination number.
The other aspect that favors the survival of vacancy loops is
that they are formed in a region with large concentration of
point defects, which leads to a reduced mobility of such loops.
Therefore, the comparison of the current MD simulations
with the experimental data on Mo (Ref. 8) shows that the
effects of the surface are significant in thin-foil experiments at
ion energies ∼102 keV due to the possibility of near-surface
production of large vacancy loops.
cascades produced by Xe ions with energies about 50 keV in
Mo single crystal with open surfaces are studied. Interstitial
clusters produced directly in the cascade are quite small (2–3
SIAs). No evidence of the large SIA cluster formations in
the early stage of cascade evolution is found, contrary to
the observations in Fe.12 The growth of clusters is possible
on the nanosecond time scale as a result of SIA diffusion
toward each other; however, most of the SIAs possess fast 1D
diffusion and can be easily lost on the surfaces. If the energy
density deposited by the ion in the vicinity of the open surface
is high enough for melting, then the spontaneous nucleation
of large vacancy dislocation loop is possible as a result of
fast recrystallization. Thus, the nature of the dislocation loops
observed agrees well with the experiments8 on ion irradiation
of Mo foils. Enhanced production of the loops for molecular
ions (at the same energy per ion) is connected with the smaller
penetration depth of molecular ions in comparison to single
ions. The mobility of the segments of the vacancy dislocation
loop is high, however, the motion of the entire loops is strongly
hindered by a number of point defects in the region where they
have been produced. Thus, it leads to the reduced mobility of
such loops and their preferential survival.
ACKNOWLEDGMENTS
The interatomic potential for Mo is presented, which takes
into account the properties of the main defect structures of
SIAs and vacancies and reproduces thermodynamic properties
in a good agreement with experimental data. Displacement
Simulations were carried out on the computing cluster
Fusion and the IBM Blue Gene/P at Argonne National
Laboratory and on the MIPT-60 cluster of the Moscow Institute
of Physics and Technology. This work was supported in part
by the US Department of Energy Office of Advanced Scientific
Computing Research, Office of Science, under Contract No.
DE-AC02-06CH11357, by the Program for Basic Research
of the RAS No. 2, Grant No. RFBR 09-08-01116, and the
President RF Grants No. MK-3174.2011.8 (A.Yu.K.) and
No. MK-6719.2010.8 (V.V.S.).
*
12
VI. CONCLUSIONS
Also at Joint Institute for High Temperatures of Russian Academy
of Sciences and Moscow Institute of Physics and Technology;
starikov@ihed.ras.ru.
†
insepov@anl.gov
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See Supplemental Material at http://link.aps.org/supplemental/
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