Introduction
The pressurized water reactor fuel assembly support structure comprises the austenitic stainless steels Solution Annealed 304 (SA 304 SS), Cold Worked 316 (CW 316 SS), and HR3 [1, 2]. The performance degradation of these engineered alloys is primarily due to the production of various defects and defect clusters introduced by neutron irradiation, in which dislocation loops are a key factor affecting their mechanical properties [3, 4]. Because the evolution of their macroscopic properties is related to the evolution of the microstructure, understanding its evolution under irradiation is essential for predicting the time of life of internals [2]. It is well known that simulating long-term microstructural evolution in systems involving dislocation loops currently relies on the CD model, which is one of the most popular models for dealing with irradiated microstructure evolution such as dislocation loops [2, 4-7].
Etienne used the CD model to quantitatively simulate the evolution of dislocation loops in 304 and 316 series stainless steels irradiated with Fe+ [2]. Although the simulation results were consistent with the experimental results, the agreement between the two sets of data was not excellent. Etienne suggested that the lack of consideration of the mobility of small point-defect clusters in the constructed CD model may be one of the reasons for the non-excellent agreement between the experimental and simulation results. According to atomistic simulations [8] and in-situ TEM observations [1, 9-11] of the mobility of irradiation-induced in-cascade clustering, small clusters (self-interstitial clusters) form directly from the irradiation cascades. The mobility of small self-interstitial clusters must be considered in the cluster dynamics model. The influence of austenitic steel interstitial cluster mobility on the evolution of dislocation loops under neutron and proton irradiation is discussed in [12] and [13]. These results demonstrate that it is reasonable to consider the mobility of interstitial clusters in the CD model.
Indeed, the irradiation and material parameters as well as the reaction mechanisms considered in the model have a key impact on the accuracy of CD simulations. The irradiation parameters include the displacement rate, irradiation dose, irradiation temperature, cascade efficiency, and in-cascade clustering directly formed by the cascade [14-16]. Subsequently, CD simulates the microstructure evolution in different materials with different values of material parameters, which plays a major role in the agreement between the CD simulation results and experimental values [5]. Material parameters such as the formation energies, point defect binding energies, and migration energies of defect clusters can be obtained by ab initio calculations, molecular dynamics calculations, or experimentally [17-19]. The irradiation and material parameters are decisive input parameters in the CD model. The reaction mechanism related to defect evolution must be properly considered in the CD model, and the mobility of small self-interstitial clusters can be considered part of the reaction mechanism.
Considering the selection of input parameters and introduction of the mobility of small self-interstitial clusters in detail, the cluster dynamics model in this study predicts the evolution of dislocation loops in austenitic steel under Fe+ irradiation. The CD model and the solution method are described in detail in Section refsec. 2. Discussions regarding the model validation and evolution mechanisms of the dislocation loops are presented in Sect. 3. Finally, a summary of this study is presented in Sect. 4.
Model descriptions
Governing equations of point defects and defect clusters
The general concept and approach of CD have been described in detail and validated in the literature [4-6, 12, 13]. The main considerations and important assumptions made in the current modeling framework are as follows:
(1) Mobile species include point defects such as self-interstitial atoms (SIA) and vacancies; small self-interstitial clusters contain two, three, and four SIAs. Only point defects can be emitted from clusters.
(2) Formation of small defect clusters (vacancy and interstitial clusters) directly from collision cascades.
(3) All mobile species exhibit 3D diffusion.
(4) For mobile interstitial clusters, the migration energy is constant and independent of their size.
(5) The pre-exponential factor of the diffusion coefficient of the interstitial clusters is the fitting parameter, which varies with the irradiation temperature and size of the interstitial clusters.
(6) Grain boundaries, dislocation lines, and surfaces are intrinsic sinks for mobile species.
The first four hypotheses in this model are based on the CD model described in detail in [12] and [13]. As stated in reference [13], the diffusion coefficient of interstitial clusters is calculated by the method in [18], the diffusion pre-exponential factor Dn0 decreases monotonically with cluster size n according to the power law Dn0=D0n-S. Ab initio research in [20] shows that as the temperature gradually increases from 200 K to 1600 K, the pre-exponential factor of the diffusion coefficient of Fe atoms in the fcc structure Ni-Fe alloy also increases. Therefore, we assume that the parameter S decreases with increasing temperature, such that the pre-exponential factor of the diffusion coefficient of small self-interstitial clusters also increases with increasing temperature; this is qualitatively consistent with the conclusion in [20]. The irradiation temperature reported in Ref. [1] are 300 ℃ and 400 ℃, while the temperature in Ref. [2] is 350 ℃. When the temperature is 300 ℃, S = 4.5, which is consistent with the value used in [13]. When the temperature is increased to 350 ℃ and 400 ℃, S is taken to be 4.3 and 4.0, respectively, through the conclusion in [20] and by fitting the calculated results with the experimental results.Grain boundary and dislocation lines are intrinsic sinks that capture mobile species [21]. A surface sink is added to the model to account for the surface effects of ion irradiation. For the sake of description, the vacancies and SIA are denoted by V and I, respectively, and small self-interstitial clusters containing two, three, and four SIAs are labeled as I2, I3, and I4, respectively. In addition, n denotes the number of point defects in a defect cluster.
Based on the above assumptions, a series of governing equations are constructed to describe the evolution of dislocation loops. The governing equations in this model for SIA and vacancy point defects are structured as follows:
The model described in Sect. 2.1 corresponds to Model-4 in this study, which represents an mobile interstitial cluster with a maximum size of four. In this study, to analyze the influence of mobile interstitial clusters on the density and size of dislocation loops predicted by the CD model, we construct three types of cluster dynamics models: those in which only a single SIA can move, those in which at most two interstitial clusters can move, and those in which interstitial clusters of size three can move; these cluster dynamics models correspond to Model-1, Model-2, and Model-3, respectively. For vacancy clusters, Model-1 to Model-4 assume that only vacancies can move. The input parameters, such as the irradiation and material parameters, are the same for Model-1 to Model-4, as shown in Table 1 and Table 2 in Sect. 2.4. The capture of mobile defects by dislocation lines, grain boundaries, and surface sinks has been considered in the four models. The main difference between the models is the size of the maximum mobile interstitial cluster. As the maximum mobile interstitial cluster gradually increases, the generation and disappearance terms required in the governing equations describing the evolution of defects of a certain size in different models change accordingly. All models assume that mobile defects undergo 3D diffusion; that is, the rates of mutual reactions between defects are calculated according to the 3D-3D expression. For brevity, Section 2 only introduces the construction of Model-4 in detail; the other three models are similar to Model-4.
Symbol | Value |
---|---|
Temperature, T (℃) | 300, 350, 400 [1, 2] |
Dose rate, Gdpa (dpa/s) | 2.9×10-4 [1, 2] |
2.2×10-3 | |
Cascade efficiency, η | 0.15 [6] |
Di-interstitial fraction in cascade, |
0.5 [6] |
Tri-interstitial fraction in cascade, |
0.2 [6] |
Four-interstitial fraction in cascade, |
0.2 [6] |
Di-vacancy fraction in cascade, |
0.05 [6] |
Tri-vacancy fraction in cascade, |
0.05 [6] |
Four-vacancy fraction in cascade, |
0.02 [6] |
Symbol | Value |
---|---|
Lattice parameter, a0 (nm) | 0.363 [27] |
Burgers vector, b | |
Vacancy formation energy, |
1.7 [2] |
Interstitial formation energy, |
4.1 [2] |
Pre-exponential factor, D0 (cm2s-1) | 10-3 [2] |
Power-law exponent, S | 4.5, 4.3*,4.0* [13] |
Vacancy migration energy, |
1.3 [29] |
Interstitial migration energy, |
0.45 [2] |
Di-interstitial binding energy, |
0.61 [2] |
Di-vacancy binding energy, |
0.45 [6] |
Dislocation density, ρdis (cm-2) | 106 [2] |
1010 | |
Average grain size, dgb (μm) | 40 [6] |
Thickness of the thin foil, 2d (nm) | 100 [2] |
Rate coefficients
The generation rates of defects from the in-cascade are taken from Ref. [6] which considered the formation of clusters with sizes greater than four unlikely. The defect-generation terms are as follows:
By adopting the formalism in Ref. [23], the rate coefficients of dislocation loops and vacancy clusters that absorb mobile defects are:
The sink strength of dislocation lines is
The expressions for the sink strengths of the grain boundary and surfaces were adopted in [26]. They can be given as:
The coupled equation, Eq. (1)- (5), along with the input parameters detailed in Sect. 2.4, are considered in the evolution system of dislocation loops involving the largest interstitial clusters I(n=117000). Thousands of equations must be solved by using this system, which requires a significant amount of simulation time. The Grouping method [30] and the Fokker-Planck method [4-6] have been used to reduce the number of equations to be solved in the system to reduce the simulation time. Parallel-solution methods reduce the simulation time of the system [31]. In this study, the discrete rate equations are transformed into Fokker-Planck equations to improve simulation efficiency. Its specific form is described in Sect. 2.3.
Fokker-Planck method
The dislocation loop evolution system described by the CD model contains a large number of ordinary differential equations(ODEs), which need to be solved. One of the main reasons for the increase in the simulation time of the cluster dynamics is the number of ODEs in the model; the more equations there are, the longer the CD simulation requires. In addition, the stiffness of the equations is also a major factor that increases the time and complexity of solving CD models. The simulation efficiency can be improved by reducing the number of equations in the system and selecting an appropriate ODE solver. The Fokker-Planck(F-P) method has been applied to reduce the number of ordinary differential equations in cluster dynamics models [4-6, 27, 32]. When the F-P method is applied, the part of the dislocation loop evolution system described by the discrete rate equations is called the discrete part, and the part that transforms the discrete rate equation into the F-P equation through Taylor expansion is the continuous part [32]. In this study, we assume that the interstitial and vacancy clusters in the discrete part range from In=1 to In=100 and
For interstitial clusters, the drift term
Input parameters
The HR3 austenitic stainless steel was irradiated with Fe+ in Ref. [1] The SA304 and CW316 stainless steels were irradiated with Fe+ in Ref. [2]. The irradiation and material parameters from the two studies can be used as input parameters for the CD model in this study, as shown in Tables 1 and 2.
Results and discussion
Effect of mobile interstitial clusters on dislocation loops evolution
Suppose that the size of the largest mobile interstitial cluster in the CD model gradually increases from one to four, corresponding to Model-1, Model-2, Model-3 and Model-4 respectively. Figure 1 shows the dislocation loop size distribution simulated by the four models at a dose of 0.145 dpa under the same irradiation conditions.
-202408(1)/1001-8042-35-08-005/alternativeImage/1001-8042-35-08-005-F001.jpg)
The ordinate in Fig. 1 is the logarithm of the dislocation loop density; therefore, the lowest density of dislocation loops cannot be considered as zero. In this study, we use
The curves in Fig. 2 and Fig. 3 show a comparison of the number density and the average diameter of the dislocation loops when the four models are simulated to 10 dpa, respectively. The scatter values are the TEM observations of the number density and average diameter of the dislocation loops, respectively, in Ref. [2].
-202408(1)/1001-8042-35-08-005/alternativeImage/1001-8042-35-08-005-F002.jpg)
-202408(1)/1001-8042-35-08-005/alternativeImage/1001-8042-35-08-005-F003.jpg)
Model-1 in Fig. 2 predicts a blue curve corresponding to the highest dislocation loop density. The dislocation loop densities predicted by Model-2 and Model-3 are indicated by red dashed and orange curves, respectively. Figure 2 shows that the dislocation loop densities predicted by Model-2 and Model-3 are almost identical, with a very small difference. In fact, the dislocation loop density predicted by Model-2 is higher than that predicted by Model-3. Compared with the other three models, Model-4 predicts the lowest dislocation loop density. In general, with an increase in the largest mobile interstitial cluster size, the number density of the dislocation loops simulated from Model-1 to Model-4 decreases. With an increase in the radiation dose, the dislocation loop density predicted by the four models gradually increased, and the growth rate of the dislocation loop density decreased; that is, the dislocation loop density tended to saturate with the increase in the dose.
In contrast to Fig. 2, compared with the other three models, the average diameter of dislocation loops predicted by Model-4 in Fig. 3 is the highest, whereas that predicted by Model-1 is the lowest. Similar to Fig. 2, the average diameters of the dislocation loops predicted by Model-3 and Model-2 were almost the same, but the average diameter of the dislocation loops predicted by Model-3 was larger than that predicted by Model-2. Therefore, in Fig. 3, the average diameter of the dislocation loops simulated from Model-1 to Model-4 increased with the increasing cluster size of the largest mobile interstitial cluster. As the irradiation dose increased, the average diameter of the dislocation loops simulated by Model-1 to Model-3 tended to stabilize after 1 dpa, with almost no growth. However, the average diameter of the dislocation loops predicted by Model-4 still has a high growth rate after 1 dpa, and does not tend to saturate even at 10 dpa; the predicted value of Model-4 is also much larger than the predicted values of the other three models.
The simulation results shown in Figs. 1, 2 and 3 can be attributed to three reasons: on the one hand, the dislocation loop number density obtained by Model-4 in Fig. 2 is the smallest; however, the average diameter of the dislocation loops obtained using Model-4 in Fig. 3 is the largest. In addition, the dislocation loop size distribution simulated by Model-1 to Model-4 in Fig. 1 evolves to a larger size at 0.145 dpa. These results indicate that increasing the size of mobile interstitial clusters can promote dislocation loop growth. In fact, the molecular dynamics simulation in [8] demonstrates that interstitial clusters can move, and the experiment in [1] demonstrates that interstitial clusters can migrate and merge to promote dislocation loop growth. Therefore, the increase in the size of the mobile interstitial clusters may be the main reason for the increase in the size of the dislocation loops simulated in Model-4. Second, with the increase in the size of mobile interstitial clusters, they are captured by dislocation loops, vacancy clusters, surfaces, grain boundaries, and dislocation line sinks, which can explain the density of dislocation loops obtained from Model-1 to Model-4 in Fig. 2 decreases with an increase in the size of the mobile interstitial clusters. Third, because the largest in-cascade interstitial cluster is assumed to be four in this study, when the mobile interstitial cluster in the CD model is less than three, an in-cascade interstitial cluster greater than three is still generated; however, an in-cascade interstitial cluster greater than three can’t be diffused and migrated. These non-migratory clusters themselves produce an accumulation, resulting in an increase in the density of dislocation loops, and also serve as a sink for mobile interstitial clusters, thus inhibiting the growth of dislocation loops to a large size distribution. This explains the reasons that lead to the almost less than 2.25 nm radius distribution of dislocation loops predicted by Model-1 to Model-3 in Fig. 1 and the average diameter of the dislocation loops predicted by Model-1 to Model-3 in Fig. 3, which consistently approximates 2 nm.
The density and average diameter of the dislocation loops in SA304 and CW316 steels irradiated by Fe+ ions observed by TEM in [2] are compared with the simulation data of Model-1 to Model-4. The experimental results agree well with the simulation results of Model-4. The reasons for the better simulation results of Model-4 may be summarized in two points. First, the fraction of in-cascade interstitial clusters obtained in [22] shows that there are few in-cascade interstitial clusters with a size greater than four; therefore, it is reasonable to assume that the maximum mobile interstitial cluster size is four. In addition, as mentioned previously, the mobility of the interstitial clusters in the model may be the main reason why the simulation results of Model-4 are in good agreement with the experimental results. The experimental results agree well with the simulation results of Model-4, indicating that it is reasonable to consider the mobility of the interstitial clusters in the CD model.
Effect of temperature on mobile interstitial clusters
In this section, the CD model(Model-4) constructed in this study is used to simulate the evolution of dislocation loops in HR3 steel, as observed during in-situ electron microscopy in [1]. Figures 4 and 5 show comparisons between the CD predictions and the experimental data for the number density and average diameter of dislocation loops at 300 ℃ and 400 ℃, respectively.
-202408(1)/1001-8042-35-08-005/alternativeImage/1001-8042-35-08-005-F004.jpg)
-202408(1)/1001-8042-35-08-005/alternativeImage/1001-8042-35-08-005-F005.jpg)
The experimental values of the number density and average diameter of the dislocation loops shown in Figs. 4 and 5 are affected by both the irradiation temperature and irradiation dose. The experimental values in Fig. 4 demonstrate that, as the temperature increases, the number density of dislocation loops decreases. This is because high temperatures promote the growth and aggregation of dislocation loops, while limiting the nucleation of new dislocation loops [1]. As mentioned in the model description, the pre-exponential factor of the diffusion coefficient of mobile interstitial clusters in this paper varies with the size of mobile interstitial clusters n and temperature T. Based on this hypothesis, T = 300 ℃, S = 4.5, T = 400 ℃, S = 4.0. With the increase in temperature, the value of S decreases and the pre-exponential factor of the diffusion coefficient of interstitial clusters increases; thus, the diffusivity of interstitial clusters increases. Enhancing the diffusion ability of interstitial clusters can promote the migration and accumulation of dislocation loops.
The CD model in Fig. 4 predicts the number density of dislocation loops under irradiation conditions of 300 ℃ and 400 ℃, respectively. With increasing temperature, the predictions of the CD model remain consistent with the experimental data. Similarly, the average diameters of the dislocation loops simulated using the CD model, as shown in Fig. 5, are in good agreement with the experimental data, and the average diameter of the dislocation loops increases with increasing temperature.
As shown in Fig. 4, the experimental value of the dislocation loop density reaches saturation at 0.5 dpa and begin to decrease with increasing radiation doses. Ref. [1] assumed that the increase of irradiation dose promotes the merging of dislocation loops and formation of network dislocations, which limits the increase in the number density of dislocation loops during irradiation. Stoller constructed an evolution model of network dislocation under irradiation, which means that the variation in network dislocation density due to the possible growth and unfaulting of dislocation loops, activation of Bardeen-Herring sources, and irradiation-enhanced climb of dislocations have been considered in [35]. The CD model in this study does not consider the network dislocation evolution, i.e., the density of network dislocations is constant. Therefore, as the irradiation dose increases, the CD model predicts that the number density of dislocation loops slowly increases and tends to saturate. This trend differs slightly from that of the experimental data for the number density of dislocation loops. In addition, the CD predictions of the average diameters of the dislocation loops still tend to grow toward larger sizes. The dislocation loop number density is slightly larger than the experimental values shown in Fig. 4 for CD simulations up to 5 dpa and 6 dpa; this may have contributed to the larger average diameter of the dislocation loops in Fig. 5 for CD predictions with irradiation doses of up to 5 dpa. Adding a network dislocation evolution mechanism to the CD model should be considered in future studies.
Conclusion
In this study, considering the mobility of interstitial clusters and selecting appropriate input parameters, a cluster dynamics model was constructed to simulate the number density and average size of dislocation loops in SA304, CW316, and HR3 austenitic steels irradiated using Fe+ ions. The main conclusions are summarized as follows:
(1) The simulation results from Model-1 to Model-4 show that as the size of the mobile interstitial cluster increases in the CD model, the dislocation loop density decreases and the dislocation loop size increases. The simulation results of Model-4 were more consistent with the experimental results in the literature. This demonstrates that it is reasonable to consider the diffusion mechanism of the interstitial clusters in the CD model.
(2) The CD simulation results of the average diameter and number density of the dislocation loops are in good agreement with the results of in-situ ion irradiation in the literature, which accurately reflects the effect of temperature on the density and size of the dislocation loops: that is, as the temperature increases, the density of the dislocation loops decreases, and the size of the dislocation loops increases.
(3) The mechanism of network dislocation evolution under irradiation is not considered in the CD model, which may be the main reason for the slight inconsistency between the simulation results of the CD model and the experimental data. Adding a network dislocation evolution mechanism to the CD model should be considered in future studies.
In-situ TEM investigation of dislocation loop evolution in HR3 steel during Fe+ ion irradiation
. J. Nucl. Mater. 578,Dislocation loop evolution under ion irradiation in austenitic stainless steels
. J. Nucl. Mater. 400, 56-63(2010). https://doi.org/10.1016/j.jnucmat.2010.02.009Spherical nanoindentation stress–strain responses of SIMP steel to synergistic effects of irradiation by H and He ions
. NUCL. SCI. TECH. 33, 79(2022). https://doi.org/10.1007/s41365-022-01053-7Rate theory study of the proton-irradiation induced dislocation loops in modified 310S steels
. Nucl. Instrum. Meth. B. 461, 181-185(2019). https://doi.org/10.1016/j.nimb.2019.09.028Microstructure modelling of ferritic alloys under high flux 1 MeV electron irradiations
. J. Nucl. Mater. 302, 143-155(2002). https://doi.org/10.1016/S0022-3115(02)00776-6Irradiation damage in 304 and 316 stainless steels: experimental investigation and modeling. Part I: Evolution of the microstructure
. J. Nucl. Mater. 326, 19-29(2004). https://doi.org/10.1016/j.jnucmat.2003.11.007Rate theory and experimental study of the irradiation induced defects in molybdenum alloy
. J. Alloys Compd. 874,Mobility of small clusters of self-interstitial atoms in dilute Fe–Cr alloy studied by means of atomistic calculations
. Comp Mater Sci. 46, 1178-1186(2009). https://doi.org/10.1016/j.commatsci.2009.06.004In-situ TEM study of the effect of pre-existing dislocation on loop evolution in 508-III steel during Fe+ irradiation
. J. Nucl. Mater. 559,Theoretical prediction of radiation-enhanced diffusion behavior in nickel under self-ion irradiation
. NUCL. SCI. TECH. 31, 79(2020). https://doi.org/10.1007/s41365-020-00791-wEffect of ion flux on one-dimensional migration of dislocation loops in Fe9Cr1.5W0.4Si F/M steel during in-situ Fe+ irradiation
. J. Nucl. Mater. 579,Modeling of microstructure evolution in austenitic stainless steels irradiated under light water reactor condition
. J. Nucl. Mater. 299, 53-67(2001). https://doi.org/10.1016/S0022-3115(01)00673-0Cascades Damage in γ-Iron from Molecular Dynamics Simulations
. MATER. SCI. FORUM. 993, 1011-1016(2020). https://doi.org/10.4028/www.scientific.net/MSF.993.1011MD and OKMC simulations of the displacement cascades in nickel
. NUCL. SCI. TECH. 27, 57(2016). https://doi.org/10.1007/s41365-016-0057-ySimulation of radiation damages in molybdenum by combining molecular dynamics and OKMC
. NUCL. SCI. TECH. 28, 3(2017).https://doi.org/10.1007/s41365-016-0164-9Helium bubble nucleation and growth in α-Fe: insights from first–principles simulations
. J. Phys. Condens. Matter. 26,Stability and mobility of defectclusters and dislocation loops in metals
. J. Nucl. Mater. 276, 65-77(2000). https://doi.org/10.1016/S0022-3115(99)00170-1Vacancy formation in iron investigated by positron annihilation in thermal equilibrium, Scr
. Metall. 11, 803-809(1977). https://doi.org/10.1016/0036-9748(77)90079-5Ab initio-based diffusion theory and tracer diffusion in Ni–Cr and Ni–Fe alloys
. J. Nucl. Mater. 405, 216-234(2010). https://doi.org/10.1016/j.jnucmat.2010.08.003Subcascade formation in displacement cascade simulations: Implications for fusion reactor materials
. J. Nucl. Mater. 271-272, 57-62(1999). https://doi.org/10.1016/S0022-3115(98)00730-2A physically based model for the spatial and temporal evolution of self-interstitial agglomerates in ion-implanted silicon
. J. Appl. Phys. 96, 4866-4877(2004). https://doi.org/10.1063/1.1786678Modeling of helium bubble nucleation and growth in neutron irradiated boron doped RAFM steels
. J. Nucl. Mater. 426, 287-297(2012). https://doi.org/10.1016/j.jnucmat.2011.12.025Integrated modeling of helium-vacancy clustering in Eurofer97 steel upon He+/Fe3+ dual-beam irradiation
. J. Nucl. Mater. 547,Effect of self-interstitial diffusion anisotropy in electron-irradiated zirconium: A cluster dynamics modeling
. J. Nucl. Mater. 346, 272-281(2005). https://doi.org/10.1016/j.jnucmat.2005.06.024A numerical solution to the Fokker-Planck equation describing the evolution of the interstitial loop microstructure during irradiation
. J. Nucl. Mater. 92, 121-135(1980). https://doi.org/10.1016/0022-3115(80)90148-8A composite model of microstructural evolution in austenitic stainless steel under fast neutron irradiation
.A critical test of the classical rate theory for void swelling
. J. Nucl. Mater. 327, 130-139(2004). https://doi.org/10.1016/j.jnucmat.2004.01.026Grouping method for the approximate solution of a kinetic equation describing the evolution of point-defect clusters
. Philos. Mag. A. 81, 643-658(2001). https://doi.org/10.1080/01418610108212164A Parallel ETD Algorithm for Large-Scale Rate Theory Simulation
. J. Supercomput. 78, 14215-14230(2022). https://doi.org/10.1007/s11227-022-04434-2Efficient simulation of kinetics of radiation induced defects: A cluster dynamics approach
. J. Nucl. Mater. 444, 298-313(2014). https://doi.org/10.1016/j.jnucmat.2013.10.009A Cluster Dynamics Model For Accumulation Of Helium In Tungsten Under Helium Ions And Neutron Irradiation
. Commun Comput Phys. 11, 1547-1568(2012). https://doi.org/10.4208/cicp.030311.090611aCVODE, A Stiff/Nonstiff ODE Solver in C
. Computers in Physics. 10, 138-143(1996).https://doi.org/10.1063/1.4822377Modeling dislocation evolution in irradiated alloys
. Metall Trans. A 21, 1829-1837(1990). https://doi.org/10.1007/BF02647229The authors declare that they have no competing interests.