• Matter and Radiation at Extremes
  • Vol. 6, Issue 1, 015902 (2021)
Sergio Davis1、2, Felipe González-Cataldo3、4, Gonzalo Gutiérrez4, Gonzalo Avaria1、2, Biswajit Bora1、2, Jalaj Jain1, José Moreno1、2, Cristian Pavez1、2, and Leopoldo Soto1、2
Author Affiliations
  • 1Comisión Chilena de Energía Nuclear, Casilla 188-D, Santiago, Chile
  • 2Departamento de Física, Facultad de Ciencias Exactas, Universidad Andres Bello, Sazié 2212, piso 7, Santiago 8370136, Chile
  • 3Department of Earth and Planetary Science, University of California, Berkeley, California 94720, USA
  • 4Grupo de Nanomateriales, Departamento de Física, Facultad de Ciencias, Universidad de Chile, Casilla 653, Santiago, Chile
  • show less
    DOI: 10.1063/5.0030158 Cite this Article
    Sergio Davis, Felipe González-Cataldo, Gonzalo Gutiérrez, Gonzalo Avaria, Biswajit Bora, Jalaj Jain, José Moreno, Cristian Pavez, Leopoldo Soto. A model for defect formation in materials exposed to radiation[J]. Matter and Radiation at Extremes, 2021, 6(1): 015902 Copy Citation Text show less

    Abstract

    A simple model for the stochastic evolution of defects in a material under irradiation is presented. Using the master-equation formalism, we derive an expression for the average number of defects in terms of the power flux and the exposure time. The model reproduces the qualitative behavior of self-healing due to defect recombination, reaching a steady-state concentration of defects that depends on the power flux of the incident radiation and the material temperature, while also suggesting a particular time scale on which the incident energy is most efficient for producing defects, in good agreement with experimental results. Given this model, we discuss the integral damage factor, a descriptor that combines the power flux and the square of the irradiation time. In recent years, the scientific community involved in plasma-facing materials for nuclear fusion reactors has used this parameter to measure the equivalent material damage produced in experiments of various types with different types of radiation and wide ranges of power flux and irradiation time. The integral damage factor is useful in practice but lacks formal theoretical justification. In this simple model, we find that it is directly proportional to the maximum concentration of defects.

    I. INTRODUCTION

    The study of materials exposed to irradiation is a broad topic whose applications are fundamental for medicine,1 astrophysics,2 and the design of nuclear reactors.3,4 The effects of radiation on materials are varied, at both the atomic and the microstructural scale, and depend mainly on the energy of the incident particles (neutrals, ions, electrons, and neutrons) impacting the surface. These effects include heating, embrittlement due to ion implantation,5 cracking and formation of voids,6 local melting and recrystallization or amorphization,7 evaporation and ablation of various types, and even different degrees of ionization. At the atomic level, radiation damage includes the formation of point, line, and volumetric defects: clusters of vacancies or interstitials, dislocation loops, stacking faults, twins, and the formation of stacking fault tetrahedra.8 Interestingly, it is well established that several of the line and volumetric defects can be traced at the atomic level to the accumulation of vacancies and interstitial defects due to radiation damage events.9,10

    A problem when designing and building a nuclear fusion reactor is selecting candidate materials for its plasma-facing components. The essential constraint is that such materials must resist extreme heat fluxes, together with high fluxes of neutrons, ion beams, and He and H isotopes such as deuterium. To test these materials, one must have access to experimental facilities that reproduce similar conditions to those expected on the materials in magnetic confinement (MC) fusion devices such as the projected ITER tokamak11 or inertial confinement (IC) fusion experiments such as those carried out at the National Ignition Facility.12,13

    The degree of damage suffered by a material under irradiation depends on several variables, including the interaction time between the plasma and the material, the peak power, and the energies deposited into the material. In practice, these quantities can vary significantly in different environments from MC to IC fusion experiments. In MC, most notably in ITER, energy loads in the divertor associated with edge localized modes14 of 100 J/cm2–300 J/cm2 are expected to have durations of 0.1 ms–0.5 ms, with 103 pulses per shot and frequencies of 0.5 Hz–2 Hz.15 In the case of IC experiments, energy loads on the chamber wall of 3 J/cm2–6 J/cm2 are expected with durations of 0.2 µs–1 µs and a frequency of around 5 Hz.16

    F=Q×t=EA×t12,where Q is the power flux, E is the energy deposited on an area A, and t is the time of interaction with the material. There is experimental evidence that a similar degree of deterioration in the material is generated in different environments when the IDF is of the same order of magnitude.18 For instance, melting was observed when tungsten was (i) irradiated in the RHEPP ion accelerator with 4.5 J/cm2 for 200 ns, (ii) irradiated with the QSPA Kh-50 plasma gun24 with 150 J/cm2 for 0.5 ms, and (iii) exposed to an energy flux of 550 J/cm2 for 3 ms in the JUDITH electron accelerator; in all three cases, the IDF was 7 kW s1/2/cm2–10 kW s1/2/cm2.18 Considering the aforementioned conditions expected in ITER and IC experiments, in both cases the expected IDF in the first wall of the reactor is around 10 kW s1/2/cm2.

    Among other irradiation facilities and devices (e.g., plasma guns, electron and ion accelerators, pulsed lasers), plasma focus (PF) devices have been used in recent years to probe these conditions because they reach similar IDF values through the high-power flux densities that they generate, thereby enabling material damage to be studied. After pinch compression, a PF device creates a plasma shock that is ejected axially and, when a material is exposed to it, can concentrate energies of 0.01 J/cm2–100 J/cm2 for interaction times of 10 ns–500 ns, depending on the distance from the anode to the target.21–23,25–27 These conditions correspond to IDFs of 1 W s1/2/cm2–104 W s1/2/cm2. Thus PF discharges can generate an equivalent material IDF to that expected in the first wall of a nuclear fusion reactor (∼10 kW s1/2/cm2).18 Although PF devices with storage energies of megajoules were originally used to produce these IDF values,28 in recent years PF scaling laws29–31 have allowed sub-kilojoule32–37 and sub-hundred-joule PF devices29,38–45 to be built, and the scaling laws have been extended down to less than 1 J.46–49 In particular, work done in the Plasma Physics and Nuclear Fusion Laboratory at the Chilean Nuclear Energy Commission30,31 has helped to show that it is possible to scale the PF in wide ranges of energy and size for given ion density, magnetic field, plasma sheath velocity, Alfvén speed, and temperature. Encouraged by these results, table-top PF devices were used to study how the plasma shock ejected axially after the pinch compression affects materials; it was found experimentally that a table-top PF device of hundreds or even only a few joules can produce the same energy densities and IDF values23,27,50 as those produced by megajoule PF devices, simply by adjusting the distance between the source and the sample. In this way, it is possible to test candidate plasma-facing materials in a table-top plasma device under the conditions expected in nuclear fusion reactors.

    Thus, regardless of the wide varieties of effects and experimental setups, it seems possible to have a global descriptor with which to estimate the degree of damage. In this sense, the IDF F appears to be a useful indicator for comparing results from experiments of different types, but unfortunately a proper theoretical explanation of this empirical fact is lacking. Although some arguments have been put forward, there is clearly a need for a sound theoretical foundation for F from the atomic phenomena of the creation and recombination of defects.

    In the present work, based on the continuous-time master equation, we propose a simple kinetic model that estimates the fraction of defects generated for a given input power flux Q and exposure time t. This model represents a starting point for understanding how F depends on the fraction of defects, giving a physical explanation for this empirical descriptor.

    II. DERIVING MODEL FOR DEFECT FORMATION FROM MASTER EQUATION

    We consider a material with N atomic sites in area A, which defines a surface atomic density of σ = N/A. The state of the sample at time t is then characterized by the number of defects n out of the total number of sites N, which defines a defect fraction x = n/N. However, because the creation and annihilation of defects is a stochastic process, we describe the state of the sample by the probability P(n|t) of having n defect sites at time t. Alternatively, we can use the fraction of defects x.

    P(n|t)t=P(n|t)ω+(n)+ω(n)+P(n+1|t)ω(n+1)+P(n1|t)ω+(n1).

    ω+(n)=ωT(β,Ev)+ηQσEvNnN,where η is a dimensionless factor that accounts for the incident energy that does not create defects, for instance, due to channeling mechanisms.53

    μ(x)=ωT+ηQσEv(1x)ωRx.

    A=ωT+ηQσEv,τ=1A+ωR.

    xeq(β)=exp(βEv)=ωTωT+ωR.

    xt,Q,β=Q1+Q1exp(t(1+Q))+xeq(β),where the exposure time t is measured in units of τ0 and Q is measured in units of Q0.

    Q1+Q1xeq(β)must be met, which naturally gives a range of applicability of the model in terms of the maximum power flux that it can describe.

    III. DISCUSSION

    In the following, we explore our model by varying its free parameters to understand how they affect the predicted number of defects in the material and how they are related to the IDF F. Varying the power flux Q and the material temperature β, we estimate the fraction of defects that can be formed for different exposure times t. We explore the limitations and range of applicability of our model.

    σ=1(3.1652Å)20.1Å2.

    Q0=σEvητ0=1.93×1010 W/cm2.Note that the value of τ0 is on the timescale required for the recombination of mobile defects, which is more than 100 ps.57

    A. Numerical exploration of model

    In Fig. 1, we show the evolution of the fraction of defects, given by Eq. (15), as a function of exposure time for different values of material temperature β = 1/kBT and power flux Q. At low temperatures (β = 10 in units of 1/Ev), condition (16) allows a wide range of Q, indicated by the different dashed blue lines. The fraction of defects approaches zero at t = 0 for any value of Q because xt=0=xeq(β)0 for low temperatures. The number of defects increases with the exposure time, reaching a steady state with a maximum number of defects ofxmax=Q1+Q+xeq(β)for long exposure times. When the power flux is increased, the steady state is reached more quickly because there is more energy available to create defects efficiently, and therefore shorter exposure times are required. The amount of defects reached in equilibrium also increases. However, when the power flux is negligible (Q = 0), we obtain the time-independent solution xt,Q,β=xeq(β), which means that the material is already in the steady state of equilibrium and has a constant number of defects equal to that created by thermal excitation only.

    Evolution of average fraction of defects, given by xt,Q,β=Q1+Q1−exp(−t(1+Q))+xeq(β) in Eq. (15), as a function of exposure time t. The temperature β = 1/kBT is expressed in units of 1/Ev, and the power flux Q is expressed in units of Q0.

    Figure 1.Evolution of average fraction of defects, given by xt,Q,β=Q1+Q1exp(t(1+Q))+xeq(β) in Eq. (15), as a function of exposure time t. The temperature β = 1/kBT is expressed in units of 1/Ev, and the power flux Q is expressed in units of Q0.

    When the temperature is increased for a given power flux (e.g., Q = 0.5 Q0 in Fig. 1), the initial fraction of defects is already greater than zero at t = 0 because of thermal excitations. Of course, the initial temperature of the material cannot be arbitrarily large for a given power flux because Eq. (16) places a limit on our model. Given this condition, the maximum temperature that can be explored for a given value of Q is βmin = 1/kBTmax = ln(1 + Q)/Ev, or equivalently, we can only explore power fluxes below Qmax = 1/xeq(β) − 1 for a given temperature β. This behavior is independent of the time and power-flux scales because these quantities have been normalized to the natural units of τ0 and Q0, respectively.

    In previous work,27 we showed experimentally that a tungsten sample located 15 mm from the anode top of our PF received a power flux of Q* = 9.2 × 106 W cm−2 = 4.76 × 10−4Q0, which interacted with the sample for t* = 75 ns = 250 τ0. In Fig. 2, we show the fraction of defects that we predict for this experiment with our model, using a temperature β = 150/Ev (T = 300 K), which leads to x(t*)=4.74×104. This value is consistent with melting, as we observed in our experiment, because a fraction of defects of between 10−4 and 10−3 is required to melt a material.54,58–60

    Average fraction of defects for Q* = 4.76 × 10−4Q0 as a function of exposure time t. The filled circle corresponds to the predicted fraction of defects for the case of tungsten exposed to power flux Q* for t* = 75 ns.27 This value is consistent with melting, as we observed in our experiment, because a fraction of defects of between 10−4 and 10−3 is required to melt a material.54,58–60

    Figure 2.Average fraction of defects for Q* = 4.76 × 10−4Q0 as a function of exposure time t. The filled circle corresponds to the predicted fraction of defects for the case of tungsten exposed to power flux Q* for t* = 75 ns.27 This value is consistent with melting, as we observed in our experiment, because a fraction of defects of between 10−4 and 10−3 is required to melt a material.54,58–60

    In Fig. 3, we show the asymptotic values to which the fraction of defects converges in the limit of long exposure time, limtxt,Q,β=xmax, given by Eq. (19). The forbidden region is determined by Eq. (16), and the combinations of Q and β that lead to the same asymptotic value xmax are indicated by the contour lines. When the power flux Q and temperature β are such that they lie on the critical (black) line that separates the forbidden region from the region of allowed values, defined by Qmax=eβEv1, the fraction of defects will always converge to xmax=1. This is, of course, an unphysical situation because having a defect in every single lattice site would violate material stability criteria. In practice, this will not happen because βEv < 10 corresponds to temperatures T > 4000 K which is well above the melting temperature of most materials. Therefore, reasonable values of β are expected to lie far from the forbidden region, which implies that the values of Q can span a wide range.

    Asymptotic values xmax as a function of free parameters Q and β. The contour lines indicate combinations of Q and β that lead to the same value of xmax.

    Figure 3.Asymptotic values xmax as a function of free parameters Q and β. The contour lines indicate combinations of Q and β that lead to the same value of xmax.

    In a recently published article,61 the kinematics of lattice defects during irradiation were modeled through the evolution of the distribution functions for different defect types. Our model captures the phenomenology of the concentration of vacancies and interstitials, which converges asymptotically to a constant value with time. According to this study,61 aggregates of vacancies are formed more efficiently under irradiation, which is consistent with Monte Carlo simulations and experimental data.62 These populations of defects can be measured indirectly through resistivity measurements63 and provide valuable information about the nature of their interaction and evolution.

    B. Damage factor F

    In the quest for a single descriptor for estimating the degree of material damage in different irradiation experiments, the IDF (sometimes known as the heat flux factor) defined byF=Qthas been proposed.3,4,17–23 Linke et al.18 argued that the same macroscopic damage events (e.g., roughening, cracking, melting) are observed at similar values of F, while Fujitsuka et al.17 suggested that the material surface temperature is proportional to Qt, which gives a measure of surface erosion resistance. This hypothesis was later shown to be valid only for constant power density (square pulses) and up to 2500 W s1/2/cm2, so F should not be used to describe surface temperature in non-square heat pulses.64 In addition to the observations in experiments using plasma guns,24 electron and ion accelerators,16 and PFs,20–23,25–27 melting and roughening were also observed in laser irradiation65 for F > 3600 W s1/2/cm2. Therefore, over a wide range, F seems to work as a simple method for normalizing the thermomechanical effects of irradiation with pulses of different durations.66

    From the observation that the same microstructural damage is observed for a given F in different experiments, we begin by testing the hypothesis that the average fraction of defects x is a function of Q and t only through Qt; that is,xQ,t=f(Qt),where f is a function to be determined. We can also construct a natural unit for the IDF, namely,F0=Q0τ0=333486Ws12/cm2.The first point from simple inspection of Eq. (15) is that the IDF hypothesis [i.e., the assumption that xt=f(Qt)] does not hold for arbitrary Q and t. However, as will be seen shortly, interpreting the IDF slightly differently makes it useful for describing material damage by radiation.

    To explore the model in terms of the IDF F, we consider isolines of fixed F=Qt, that is, where the flux Q can be expressed as a function of the exposure time t byQ(t,F)=F/t.Replacing Q(t, F) in Eq. (15), we obtain xt as a function of t along these contour lines, which are shown in Fig. 4. Here we see that with increasing exposure time t for a given F (therefore decreasing Q), there is an optimum exposure time t* that maximizes the average number of defects produced. This is expected because recombination mechanisms dominate for longer exposure times. Interestingly, this maximum value of xt, denoted in the following by xmax and corresponding to an exposure time t = t*, is in fact determined solely by the value of F, i.e., xmax = xmax(F), as shown in Fig. 5.

    Average fraction of defects as a function of exposure time for different values of integral damage factor (IDF) F.

    Figure 4.Average fraction of defects as a function of exposure time for different values of integral damage factor (IDF) F.

    Maximum fraction of defects as a function of IDF F=Qt. The behavior is linear in accordance with Eq. (25).

    Figure 5.Maximum fraction of defects as a function of IDF F=Qt. The behavior is linear in accordance with Eq. (25).

    Moreover, for F/F0 ≪ 1, this maximum fraction of defects is linear with F, as shown in Fig. 6. We can understand this by maximizing x with respect to t while replacing Q=Q(t)=F/t with fixed F. The resulting maximum average fraction of defects x* is implicitly only a function of F. After some algebra, the first derivative of x* with respect to F at F = 0 is given byddFx*(F)F=0=2u01+2u02=α,where u0 is the non-zero solution of the transcendental equation exp(u02)=1+2u02 (i.e., u0 ≈ 1.120 906 423), giving α = 0.638 172 686. In this way, for a fraction of defects below 2%, the linear approximationxmax(F)αFF0holds, where α ≈ 0.64. For melting to occur, it is well known that a fraction of defects between 10−4 and 10−3 is needed,54,59 so the linear approximation should be good enough in the case of radiation-induced melting. Beyond this linear approximation, the exact equations are given in Appendix B. A more familiar scale for the damage in a material can be produced by defining an “effective temperature” as a function of the maximum fraction of defects with given F. For this, we identifyxmax(F)=exp(Ev/kBTeffmax(F)),leading toTeffmax(F)=EvkBln(xmax(F))EvkBlnF0/(αF).

    Maximum fraction of defects as a function of normalized IDF F/F0, up to F = 0.6 F0. The blue curve is the numerical solution of Eqs. (B1) and (B2), and the orange curve is the linear approximation in Eq. (25).

    Figure 6.Maximum fraction of defects as a function of normalized IDF F/F0, up to F = 0.6 F0. The blue curve is the numerical solution of Eqs. (B1) and (B2), and the orange curve is the linear approximation in Eq. (25).

    In other words, Teffmax(F) is the temperature needed to achieve the same fraction of thermal defects in the material as that produced by incident radiation at an IDF F. Of course, this scale depends on the material through Ev, the energy cost of producing a defect. Figure 7 shows this effective temperature computed using Eq. (27) as a function of F.

    Maximum effective temperature as a function of IDF, computed by matching xmax(F) to exp(−Ev/kBTeff).

    Figure 7.Maximum effective temperature as a function of IDF, computed by matching xmax(F) to exp(−Ev/kBTeff).

    We can also associate an arbitrary fraction of defects with an effective temperature through xt=exp(Ev/kBTeff) for a given F. We show this effective temperature Teff as a function of exposure time t in Fig. 8 along the lines of constant F, where we observe how the effective temperature attains the maximum Teffmax that we discussed in Fig. 7. Because xt(F)<xmax(F) for any exposure time t at a given F, we have Teff(F)<Teffmax(F). Therefore, for a fixed value of the IDF in Fig. 7, we have a range of smaller possible values of xt that are associated with smaller effective temperatures Teff, with Teffmax being the maximum temperature (number of defects) that can be produced for a given F. Note that these values are degenerate because, as can be seen in Fig. 4, two different values of t are compatible with the same value of xt; hence, for a given F, two values of t are possible for the same effective temperature Teff.

    Effective temperature Teff(F)=Ev/kBln(1/xt(F)) as a function of exposure time t along lines of constant IDF F (measured in units of W s1/2/cm2).

    Figure 8.Effective temperature Teff(F)=Ev/kBln(1/xt(F)) as a function of exposure time t along lines of constant IDF F (measured in units of W s1/2/cm2).

    IV. CONCLUSIONS

    We have developed a simple model for the kinetics of the fraction of defects as a function of the input power flux Q and the exposure time t. The model considers the creation of defects due to the incident radiation and also their recombination due to thermal mobility. Interestingly, the model is irrespective of irradiation type (e.g., electrons, ions, plasma shocks, heat flux, electromagnetic radiation, laser light), depending on only the energy of defect formation and not on the specific type of defect. In this way, we obtained a formula [Eq. (15)] for the average number of defects in terms of the incident power flux, the material temperature, and the irradiation time.

    We predict that for any given power flux, the material reaches a steady state after a long exposure time, where the fraction of defects stays constant, because of the equilibrium between the creation and recombination of defects. As the material temperature increases, the material reaches a new steady state with more defects. The number of defects that our model predicts is consistent with observations of melting in PF experiments for the same power flux and exposure time, in terms of the expected fraction of defects for melting to occur.

    According to the assumptions of our model, the maximum fraction of defects increases as the IDF increases, and the dependence is roughly linear below F/F0 ∼ 0.1, which means that the creation of defects is not as efficient for high values of IDF. Of course, xmax cannot increase indefinitely, so we may consider that our model is no longer valid above some threshold of defect concentration. Above this threshold, our model breaks down and a different phenomenology, other than defect formation, must be considered.

    The description of the IDF from this model supports the observations from experiments of various types with different types of radiation and wide ranges of values for the power flux and irradiation time. More interestingly, it also supports the use of table-top PF devices to test candidate plasma-facing materials under the conditions expected in nuclear fusion reactors. In this way, it is possible to perform these tests in small-scale laboratories, including table-top experiments, which was previously possible only in large experimental facilities.

    We also acknowledge that our model does not include other type of defects, such as divacancies or clusters of vacancies, dislocations, or the effect of grain boundaries. However, it constitutes a starting point that allows us to understand the connection between atomic processes and macroscopic measurements of damage induced by radiation in the context of plasma-facing materials, as well as the physical meaning of the IDF descriptor.

    APPENDIX A: FIRST MOMENT OF ADVECTION EQUATION

    We begin with the one-dimensional continuity equation for a random variable x ∈ [0, 1] with drift coefficient μ(x):?P(x|t)?t+??xμ(x)P(x|t)=0.Multiplying both sides by x and integrating from x = 0 to 1, we have01dx?x?P(x|t)?t+01dx?x??xμ(x)P(x|t)=0.In the first term, we exchange the partial derivative in t and the integration, giving??txt+01dx?x??xμ(x)P(x|t)=0.The second term can be solved using integration by parts, namely,01dx?x??xμ(x)P(x|t)=μ(x)P(x|t)x01?01dxμ(x)P(x|t)=?μ(x)t,because of the boundary conditions P(x = 0|t) = 0 and P(x = 1|t) = 0, finally giving??t?x?t=?μ(x)?t.

    APPENDIX B: NONLINEAR MODEL

    We take the average fraction of defects in Eq. (15) and, after defining u(t)=t and eliminating Q by using F = u?·?Q, write it asxu,F=F(F+2u)1+(F+2u)(F+u)+xeq(β),with u given also implicitly as a function of F by the transcendental equationexp(?u(F+u))=11+(F+2u)(F+u).Setting F = 0 in this transcendental equation gives the equation for the constant u0 in the main text, and the expression for the first derivative of x* with respect to F when F → 0 [Eq. (24)] is obtained by differentiating Eq. (B1) implicitly and then taking the limit.

    References

    [1] V. A. Gribkov, M. A. Orlova, O. A. Kost et al. Enzyme activation and inactivation induced by low doses of irradiation. Appl. Biochem. Biotechnol., 88, 243-255(2000).

    [2] S. C. Bott, D. M. Haas, J. Kim et al. Supersonic jet formation and propagation in x-pinches. Astrophys. Space Sci., 336, 33-40(2011).

    [3] I. V. Borovitskaya, V. A. Gribkov, E. V. Demina et al. Application of dense plasma focus devices and lasers in the radiation material sciences for the goals of inertial fusion beyond ignition. Matter Radiat. Extremes, 5, 045403(2020).

    [4] R. Gonzalez-Arrabal, A. Rivera, J. M. Perlado. Limitations for tungsten as plasma facing material in the diverse scenarios of the European inertial confinement fusion facility HiPER: Current status and new approaches. Matter Radiat. Extremes, 5, 055201(2020).

    [5] M. P. Short, Y. Li, Y. Yang et al. Ion radiation albedo effect: Influence of surface roughness on ion implantation and sputtering of materials. Nucl. Fusion, 57, 016038(2017).

    [6] G. Cheng, W. Xu, Y. Zhang et al. In-situ atomic-scale observation of irradiation-induced void formation. Nat. Commun., 4, 2288(2013).

    [7] E. Artacho, K. Trachenko, M. T. Dove et al. Atomistic simulations of resistance to amorphization by radiation damage. Phys. Rev. B, 73, 174207(2006).

    [8] E. Figueroa, G. Gutiérrez, E. Bringa, D. Tramontina. Mechanical properties of irradiated nanowires—A molecular dynamics study. J. Nucl. Mater., 467, 677-682(2015).

    [9] R. G. Hoagland, A. F. Voter, S. M. Valone, B. P. Uberuaga. Direct transformation of vacancy voids to stacking fault tetrahedra. Phys. Rev. Lett., 99, 135501(2007).

    [10] G. S. Was. Fundamentals of Radiation Materials Science(2017).

    [11] B. Verberck. Building the way to fusion energy. Nat. Phys., 12, 395-397(2016).

    [12] E. I. Moses. Advances in inertial confinement fusion at the National Ignition Facility (NIF). Fusion Eng. Des., 85, 983-986(2010).

    [13] O. A. Hurricane, D. T. Casey, D. A. Callahan et al. Fuel gain exceeding unity in an inertially confined fusion implosion. Nature, 506, 343-348(2014).

    [14] A. W. Leonard. Edge-localized-modes in tokamaks. Phys. Plasmas, 21, 090501(2014).

    [15] C. H. Skinner, G. Federici, J. N. Brooks et al. Plasma-material interactions in current tokamaks and their implications for next step fusion reactors. Nucl. Fusion, 41, 1967(2001).

    [16] A. Rivera, J. Alvarez, R. González-Arrabal et al. Potential common radiation problems for components and diagnostics in future magnetic and inertial confinement fusion devices. Fusion Eng. Des., 86, 1762-1765(2011).

    [17] M. Fujitsuka, H. Shinno, T. Tanabe, H. Shiraishi. Thermal shock experiments for carbon materials by electron beams. J. Nucl. Mater., 179-181, 189-192(1991).

    [18] J. Linke, I. V. Mazul, F. Escourbiac et al. High heat flux testing of plasma facing materials and components—Status and perspectives for iter related activities. J. Nucl. Matter, 367, 1422-1431(2007).

    [19] V. Pelõhh, T. Barashkova, T. Laas. Methods for estimating the damage factor of materials under the influence of plasma, 22-24(2010).

    [20] B. Bienkowska, V. A. Gribkov, M. Borowiecki et al. Plasma dynamics in PF-1000 device under full-scale energy storage: I. Pinch dynamics, shock-wave diffraction, and inertial electrode. J. Phys. D: Appl. Phys., 40, 1977-1989(2007).

    [21] V. N. Pimenov, L. I. Ivanov, S. A. Maslyaev et al. Surface and bulk processes in materials induced by pulsed ion and plasma beams at dense plasma focus devices. Nukleonika, 51, 71-78(2006).

    [22] V. N. Pimenov, S. A. Maslyaev, E. V. Demina et al. Damage and modification of materials produced by pulsed ion and plasma streams in dense plasma focus device. Nukleonika, 53, 111-121(2008).

    [23] J. Moreno, C. Pavez, L. Soto et al. Characterization of the axial plasma shock in a table top plasma focus after the pinch and its possible application to testing materials for fusion reactors. Phys. Plasmas, 21, 122703(2014).

    [24] O. V. Byrka, A. N. Bandura, I. E. Garkusha et al. Damage to preheated tungsten targets after multiple plasma impacts simulating iter elms. J. Nucl. Mater., 386, 127-131(2009).

    [25] V. A. Gribkov, L. I. Ivanov, V. N. Pimenov et al. Interaction of high temperature deuterium plasma streams and fast ion beams with stainless steels in dense plasma focus device. J. Phys. D: Appl. Phys., 36, 1817(2003).

    [26] V. Shirokova, T. Laas, A. Ainsaar et al. Comparison of damages in tungsten and tungsten doped with lanthanum-oxide exposed to dense deuterium plasma shots. J. Nucl. Matter, 435, 181-188(2013).

    [27] M. J. Inestrosa-Izurieta, E. Ramos-Moore, L. Soto. Morphological and structural effects on tungsten targets produced by fusion plasma pulses from a table top plasma focus. Nucl. Fusion, 55, 093011(2015).

    [28] S. Lee, A. Serban. Dimensions and lifetime of the plasma focus pinch. IEEE Trans. Plasma Sci., 24, 1101-1105(1996).

    [29] L. Soto, P. Silva, W. Kies, J. Moreno. Pinch evidence in a fast and small plasma focus of only tens of joules. Plasma Sources Sci. Technol., 13, 329(2004).

    [30] L. Soto. New trends and future perspectives on plasma focus research. Plasma Phys. Controlled Fusion, 47, A361(2005).

    [31] C. Pavez, L. Soto, A. Tarifeño et al. Studies on scalability and scaling laws for the plasma focus: Similarities and differences in devices from 1 MJ to 0.1 J. Plasma Sources Sci. Technol., 19, 055017(2010).

    [32] L. Soto, P. Silva, J. Moreno et al. Neutron emission from a fast plasma focus of 400 Joules. Appl. Phys. Lett., 83, 3269-3271(2003).

    [33] J. Pouzo, M. Milanese, R. Moroso. DD neutron yield in the 125 J dense plasma focus nanofocus. Eur. Phys. J. D, 27, 77-81(2003).

    [34] R. S. Rawat, R. Verma, P. Lee et al. Experimental study of neutron emission characteristics in a compact sub-kilojoule range miniature plasma focus device. Plasma Phys. Controlled Fusion, 51, 075008(2009).

    [35] M. Zambra, J. Pedreros, C. Pavez et al. Potentiality of a small and fast dense plasma focus as hard x-ray source for radiographic applications. Plasma Phys. Controlled Fusion, 54, 105018(2012).

    [36] V. Tang, J. L. Ellsworth, S. Falabella et al. Design and initial results from a kilojoule level dense plasma focus with hollow anode and cylindrically symmetric gas puff. Rev. Sci. Instrum., 85, 013504(2014).

    [37] H. Acuña, H. Bruzzone, M. Barbaglia et al. Experimental study of the hard x-ray emissions in a plasma focus of hundreds of joules. Plasma Phys. Controlled Fusion, 51, 045001(2009).

    [38] J. Moreno, P. Silva, L. Soto et al. A plasma focus driven by a capacitor bank of tens of joules. Rev. Sci. Instrum., 73, 2583-2587(2002).

    [39] T. Sakamoto, Y. Kobayashi, S. R. Mohanty et al. Miniature hybrid plasma focus extreme ultraviolet source driven by 10 kA fast current pulse. Rev. Sci. Instrum., 77, 043506(2006).

    [40] L. Soto, P. Silva, J. Moreno et al. Demonstration of neutron production in a table-top pinch plasma focus device operating at only tens of joules. J. Phys. D: Appl. Phys., 41, 205215(2008).

    [41] P. Lee, R. S. Rawat, R. Verma et al. Miniature plasma focus device as a compact hard x-ray source for fast radiography applications. IEEE Trans. Plasma Sci., 38, 652-657(2010).

    [42] R. Shukla, S. K. Sharma, P. Banerjee et al. Low voltage operation of plasma focus. Rev. Sci. Instrum., 81, 083501(2010).

    [43] M. Krishnan, C. James, B. L. Bures. A plasma focus electronic neutron generator. IEEE Trans. Plasma Sci., 40, 1082-1088(2012).

    [44] L. Soto, A. Tarifeño-Saldivia. Statistical characterization of the reproducibility of neutron emission of small plasma focus devices. Phys. Plasmas, 19, 092512(2012).

    [45] R. K. Rout, P. Mishra, R. Niranjan et al. Palm top plasma focus device as a portable pulsed neutron source. Rev. Sci. Instrum., 84, 063503(2013).

    [46] J. Moreno, C. Pavez, L. Soto et al. Nanofocus: An ultra-miniature dense pinch plasma focus device with submillimetric anode operating at 0.1 J. Plasma Sources Sci. Technol., 18, 015007(2008).

    [47] L. Soto, C. Pavez. Demonstration of x-ray emission from an ultraminiature pinch plasma focus discharge operating at 0.1 J nanofocus. IEEE Trans. Plasma Sci., 38, 1132-1135(2010).

    [48] H. N. Acuña, H. Bruzzone, M. O. Barbaglia et al. Electrical behavior of an ultralow-energy plasma-focus device. IEEE Trans. Plasma Sci., 42, 138-142(2014).

    [49] C. Pavéz, L. Soto, J. Moreno et al. Evidence of nuclear fusion neutrons in an extremely small plasma focus device operating at 0.1 Joules. Phys. Plasmas, 24, 082703(2017).

    [50] L. Soto, S. Davis, C. Pavez et al. Material studies for inertial fusion devices using pulsed plasma shocks from a repetitive table top plasma focus device, 187-203(2019).

    [51] R. Zwanzig. Nonequilibrium Statistical Mechanics(2001).

    [52] N. G. Van Kampen. Stochastic Processes in Physics and Chemistry(2007).

    [53] T. S. Noggle, O. S. Oen. Reduction in radiation damage due to channeling of 51-MeV iodine ions in gold. Phys. Rev. Lett., 16, 395(1966).

    [54] M. Hillert. Phase Equilibria, Phase Diagrams and Phase Transformations(2007).

    [55] S. Davis, A. Rosengren, B. Johansson, A. B. Belonoshko. Model for diffusion at the microcanonical superheating limit from atomistic computer simulations. Phys. Rev. B, 84, 064102(2011).

    [56] J. Fikar, R. Schäublin. Molecular dynamics simulation of radiation damage in bcc tungsten. J. Nucl. Matter, 386, 97-101(2009).

    [57] K. Nordlund, A. E. Sand, S. J. Zinkle et al. Primary radiation damage: A review of current understanding and models. J. Nucl. Matter, 512, 450-479(2018).

    [58] R. W. Balluffi, R. O. Simmons. Measurement of equilibrium concentrations of vacancies in copper. Phys. Rev., 129, 1533(1963).

    [59] S. Davis, M. J. Pozo, J. Peralta. Statistical distribution of thermal vacancies close to the melting point. Physica A, 457, 310-313(2015).

    [60] Y. P. Mitrofanov, R. A. Konchakov, E. V. Safonova et al. Experimental evidence for thermal generation of interstitials in a metallic crystal near the melting temperature. J. Phys.: Condens. Matter, 28, 215401(2016).

    [61] M. V. Sorokin, V. I. Dubinko, K. Schwartz et al. Kinetics of lattice defects induced in lithium fluoride crystals during irradiation with swift ions at room temperature. Nucl. Instrum. Methods Phys. Res., Sect. B, 466, 17-19(2020).

    [62] V. Kashcheyevs, V. N. Kuzovkov, E. A. Kotomin et al. Modeling of primary defect aggregation in tracks of swift heavy ions in LiF. Phys. Rev. B, 64, 144108(2001).

    [63] J. D. Torre, C.-C. Fu, F. Willaime et al. Multiscale modelling of defect kinetics in irradiated iron. Nat. Mater., 4, 68-74(2004).

    [64] R. P. Doerner, G. De Temmerman, J. H. Yu et al. The effect of transient temporal pulse shape on surface temperature and tungsten damage. Nucl. Fusion, 55, 093027(2015).

    [65] G. G. Van Eden, T. W. Morgan, H. J. Van Der Meiden et al. The effect of high-flux H plasma exposure with simultaneous transient heat loads on tungsten surface damage and power handling. Nucl. Fusion, 54, 123010(2014).

    [66] A. Rivera, D. Garoz, A. R. Páramo et al. Modelling the thermomechanical behaviour of the tungsten first wall in HiPER laser fusion scenarios. Nucl. Fusion, 56, 126014(2016).

    Sergio Davis, Felipe González-Cataldo, Gonzalo Gutiérrez, Gonzalo Avaria, Biswajit Bora, Jalaj Jain, José Moreno, Cristian Pavez, Leopoldo Soto. A model for defect formation in materials exposed to radiation[J]. Matter and Radiation at Extremes, 2021, 6(1): 015902
    Download Citation