- Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin, China
Fuel–coolant interaction (FCI) has a pivotal role in the development of core disruptive accident in a sodium-cooled fast reactor. The drastic deformation of multiphase interface in the FCI is hard to deal with in the traditional grid method. In this paper, an improved multiphase smoothed particle hydrodynamics (SPH) algorithm corrected with the kernel gradient correction (KGC) technique is presented for multiphase flow with a large density ratio and complex interfacial behaviors. The density discontinuity across the multiphase interface is described with the use of special volume, which only depends on the position information of adjacent particles. This multiphase SPH algorithm, which is troubled by an unstable and mixed-interface problem under a large density ratio, is significantly improved with the KGC technique. The accuracy and robustness of the improved method are demonstrated in the numerical simulations of the deformation of a square droplet, Rayleigh–Taylor instability, and bubble rising in water. The verified corrected multiphase SPH is applied to simulate the hydrodynamic behaviors of the general FCI and the interaction between fuels coated with stainless steel film and coolant. Boundary layer stripping, Rayleigh–Taylor instability, and Kelvin–Helmholtz instability are observed as important mechanisms of hydraulic fracturing. The fragments’ distribution and the influence of stainless steel film are analyzed. The existence of a stainless steel film has been shown to inhibit breakage.
1 Introduction
As the most mature reactor of Generation-IV advanced reactor systems, a sodium-cooled fast reactor (SFR) has advantages such as good inherent safety, high breeding ratio, high thermal conductivity, and long-life radioactive waste transmutation. Rich experience with operating systems laid the foundation of its commercialization. However, once the anticipated transients without scram, including unprotected transient overpower and unprotected loss of flow, happened, the boiling coolant could cause an increase in reactivity, exacerbating the consequences and leading to core disruption and fuel melting (Tobita et al., 2016). Although the probability of core disruptive accident (CDA) is very low, it is crucial for reactor safety assessment. Molten fuel ejected from the cladding rupture is mixed with the coolant and forms fragments. The behavior and size of fuel fragments formed in the fuel–coolant interaction (FCI) significantly affect the heat transfer deterioration in core as well as cooling and re-criticality in the lower head and core catcher (Cheng et al., 2019).
From this point of view, a number of experimental research studies have been conducted on the FCI related to an SFR to figure out the fragmentation characteristics over the past decades (Iwasawa and Abe, 2018). Some researchers used molten fuel materials (U/UO2) in pursuit of a realistic core condition. Armstrong reported a series of experiments about the interactions between UO2/stainless steel and liquid sodium in a dropping mode (Armstrong 1971) (Armstrong et al., 1976). Gabor et al. (1988) performed experiments by pouring molten metallic fuel and its alloy in quantities of kilogram into a sodium pool and focused on breakup behaviors. In most of the later experiments, as core materials are not readily available, materials with physical properties similar to fuel, such as copper, were often used as substitutes (Schins and Gunnerson, 1986; Nishimura et al., 2007; Nishimura et al., 2010; Zhang and Sugiyama, 2012). The fragmentation mechanisms are usually inferred based on the size and morphology of the solid fragments. Nishimura et al. (2010) carried out the FCI experiment in the form of a single molten copper jet penetrating into a sodium pool and analyzed the fragmentation characteristics from hydraulic and thermal perspectives. The processes of a single molten copper droplet (Nishimura et al., 2007; Zhang et al., 2009; Zhang and Sugiyama, 2010; Zhang and Sugiyama, 2012) and continuous copper droplets (Yang et al., 2018; Yang et al., 2019) interacting with liquid sodium have also been studied, and a thermal fragmentation mechanism of sodium entrainment was proposed and fragmentation due to a sodium microjet was presented.
In order to get rid of the limitation of core materials and obtain a visible development process, some scholars chose numerical methods to study the FCI. Cheng et al. (2015b) used SIMMER-III, which is a safety analysis code characterized by multivelocity field, multiphase, and multicomponent modeling to simulate the experimental tests of fuel–water interaction conducted at the Japan Atomic Energy Agency (Cheng et al., 2015a), to figure out the characteristics including pressure buildup and mechanical energy release. Because the FCI is a complex phenomenon involving multiphase flow, intense interfacial motion, drastic heat transfer, and phase transitions, it is challenging for traditional grid methods to capture these details, and some technical limitations emerge, such as grid distortion in the Lagrange grid method or difficult interface tracking in the Euler grid method when dealing with such large deformation multiphase flow problems. Therefore, some scholars have turned to meshfree methods, which have received extensive attention in recent years. The computational domain of the particle method is represented by a series of randomly distributed particles carrying material properties. Due to these moving Lagrange particles, the meshfree particle methods obtain attractive features and inherent advantages in solving complex hydrodynamics problems. The moving particle semi-implicit (MPS) method and smoothed particle hydrodynamics (SPH) are two typical meshfree particle methods. MPS was first proposed by Koshizuka and Oka (1996) and focused on thermal–hydraulic simulations in nuclear field. Abundant models related to incompressible flow have been developed in the MPS framework for calculating surface tension, heat conduction and convection, open inlet and outlet boundaries, fluid–structure interaction, and other problems. The development and application of MPS in nuclear engineering are well-reviewed by Li et al. (2020). SPH is the first meshfree particle method proposed by Lucy (1977) and Gingold and Monaghan (1977). With sufficient development, it has been widely used in marine, aerospace, and other fields covering compressible, weakly compressible, and incompressible flows (Lind et al., 2020). The fundamental difference between MPS and SPH lies in the solution of pressure. The pressure of incompressible flow in MPS is calculated by implicitly solving the pressure Poisson equation, which requires solving a super large-scale matrix. It is a severe test of computational cost and parallel feasibility, especially with a huge number of particles (Li et al., 2020). Considering the large-scale particle computation and parallel algorithms are the general trend, although SPH is rarely used in nuclear field compared with MPS, SPH is chosen in this paper for its development potential with explicit solution, which makes it easy to improve the computational efficiency through parallelism. In order to handle the density discontinuity across the multiphase interface, a few solutions have been proposed. In this paper, one of the popular ideas based on particle number density is adopted (Hu and Adams, 2006; Hu and Adams, 2007; Szewc et al., 2015). However, there are still errors under this approximation idea, and the accumulated errors lead to the situation where the stability and accuracy of the calculation cannot be maintained for a long time. Therefore, this study introduced kernel gradient correction (KGC) and combined it with the use of particle number density. The significantly better performance of the improved method in dealing with multiphase flow has been demonstrated and emphasized. The multiphase SPH corrected with KGC is abbreviated as KGC-MSPH in this paper. The program in this paper is developed based on FORTRAN language and uses OpenMP to realize parallel computation.
This paper is organized as follows: in the second section, the basic physical models, namely, conservation equations and equations of state, are introduced. Then, the third section describes the numerical scheme, including the basic principle of SPH and models and corrections used in multiphase SPH. In the fourth section, the numerical investigation of KGC-MSPH is explained with the test cases. Finally, we apply the validated method to the simplified FCI condition and discuss the simulation results.
2 Physical models
The Navier–Stokes equations used to describe the flow system in a Lagrangian frame are applied. The continuity equation and the momentum equation are as follows:
where
where,
3 Numerical scheme
3.1 Basic principle of SPH
In SPH, the computational domain is represented by a finite number of particles, which carry physical properties like real fluid elements. A kernel function is applied to establish the relationship between particles. The kernel approximation works by integrating over the surrounding particles to express the central one. The arbitrary function
where,
The kernel function plays an important role in the SPH simulation and significantly affects the numerical results. Here, we consider two kernel functions. One is the renormalized Gaussian kernel (Grenier et al., 2009; Molteni and Colagrossi, 2009) used in the deformation of square droplet, given as follows:
where,
The other one is the Wendland kernel (Dehnen and Aly, 2012; Ferrand et al., 2013) used in the other cases, given as
where, the cut-off radius is set to be
3.2 MSPH formulations
The density estimation is the basis in the SPH frame and is achieved either by the continuity equation or by the density summation approach. In order to handle the density discontinuity across the multiphase interface, a few variants of density estimation have been developed. The special volume proposed by Hu and Adams (2006) is used in the present work. It is based on the density summation theory with the use of an interpolating function, given as
where,
After the aforementioned derivation, the special volume
The density of particle
Based on the multiphase SPH idea, the momentum conservation equation Eq. 2 can be discretized as,
The acceleration term driven by the pressure gradient in Eq. 11 has the anti-symmetric form, which is variationally consistent with the form of density estimation.
In addition to density, some other physical properties are discontinuous across the multiphase interface, such as viscosity. To deal with the viscosity jump, the viscous coefficient is calculated in a harmonic mean form proposed by Hu and Adams (2006). The formula of the viscous force
where,
Here, the surface tension force is calculated using the CSF model (Brackbill et al., 1992) in the form
where,
The curvature
where,
The good performance of this surface tension model in multiphase flow is demonstrated in this study by simulating the oscillatory deformation of a square droplet.
3.3 Time-stepping scheme
The time-stepping scheme is fully explicit. Similar to Zhang et al. (2015), a modified predictor-corrector time-stepping scheme is used in this paper to integrate Eqs 1, 2. The integration process is divided into two steps. The following equation gives the prediction step of the algorithm.
where, the subscripts
3.4 Solid boundary treatment
In this paper, the solid boundary condition is carefully set with ghost particles, which have a mirroring relationship with the fluid particles within
where, the distance between the ghost particle and the fluid particle is calculated as
3.5 Kernel gradient correction
Kernel gradient correction was developed to improve the simulation accuracy, and Bonet and Lok (1999) proved that by theoretical derivation. Shao et al. (2012) and Zhang and Liu (2017) have applied KGC in SPH simulation of liquid sloshing dynamics, high velocity impact, and violent impinging flow problems (Shao et al., 2016), which all focus on single-phase flow problems. Zhu et al. (2018) presented a SPH model for simulating multiphase flows with the use of KGC. In their work, the density is evaluated by the continuity equation, and the interface sharpness was maintained by developing an interface treatment algorithm, which consists of a virtual particle technique and an interface force. Here, the density discontinuity is handled by calculating the special volume based on density summation idea. The introduction of KGC can significantly improve the multiphase SPH model in this work, and the solution procedure of KGC-MSPH is relatively simple. The remarkable performance of KGC will be discussed in the numerical cases. The KGC formulation can be derived as follows:
The corrected kernel gradient can be obtained by modifying the original gradient with a reversible matrix,
Since the
3.6 The interfacial repulsive force
The interfacial repulsive force is commonly used in multiphase SPH-related studies (Monaghan, 2000; Grenier et al., 2009). If surface tension force is not considered, a spurious fragmentation can happen on the interface. The application of interfacial repulsive force can maintain the interface sharpness. This repulsive force is added to the pressure term depending on different situations and requirements. The discretized momentum equation considering the interfacial repulsive force can be written as follows:
The interfacial repulsive force only appears near the interface and vanishes if the neighbor particles belong to the same phase. The effect of the interfacial repulsive force is negligible on the surface tension force, and the magnitude of the force is determined by the coefficient
4 Numerical investigations
4.1 Deformation of square droplet
In this section, the KGC-MSPH method is analyzed and verified by a 2D simulation of the deformation of a square droplet. This case has been studied by Ming et al. (2017), and Patiño-Nariño et al. (2019) simulated a simple case of a circle drop resettling under a zero gravity condition. The multiphase SPH models adopted in their work are also based on calculations of particle number density and specific volumes. Distorted and mixed-interface problem plagued them. In order to maintain the sharpness under the high density ratio and suppress the instabilities, some treatments, like background pressure and interface sharpness control and inter-particle approximation of average pressure value, are applied in their simulations. Here, we use the same case to demonstrate the effectiveness of KGC on this problem and make comparative analysis with their treatments.
The initial condition is shown in Figure 1. A square droplet with side length
For comparison, the MSPH basic method without correction is used in this case where
FIGURE 4. The variation of total kinetic energy of the droplet deformation with different density ratio and viscosity ratio.
4.2 Rayleigh–Taylor instability
In order to further demonstrate the good performance of KGC-MSPH in gravity flow, we select a classic case, Rayleigh-Taylor (R–T) instability, which has been studied by Cummins and Rudman (1999), Grenier et al. (2009), and Hu and Adams (2009) in many ways. The computational domain is rectangular with size of 1.0
With KGC modification, MSPH is qualified for simulating R–T instability, and the contour of the interphase interface is well-described. The variation of the highest front position of the lighter fluid is in good agreement with the Layzer theory as shown in Figure 6. Because no external force is applied to the interface, slight unsmoothness occurred as shown in Figure 7A. The repulsive force model commonly used by scholars (Monaghan, 2000; Grenier et al., 2009; Monaghan and Rafiee, 2013) to stabilize multiphase interfaces was introduced. Snapshots of simulation results under repulsive forces of varying magnitude with
FIGURE 7. Snapshots of R-T instability at t = 5.0 s obtained by A MSPH-KGC, B MSPH-KGC with repulsive force ε = 0.01, C MSPH-KGC with repulsive force ε = 0.08.
We can conclude in this section that KGC-MSPH is capable of simulating R–T instability problem. The KGC correction fundamentally stabilizes the calculation and improves the calculation accuracy. If a smooth interface is desired, surface tension can be applied or an appropriate repulsive force can be introduced.
4.3 Bubble rising
Bubble dynamics plays an important role in multiphase flow. The bubble rising problem has been studied with experiments, such as Collins (1967); Liu et al. (2016), and it has been extensively simulated, such as Sussman et al. (1994) with a level set method and Krishna et al. (2000) with a VOF method. As an important multiphase benchmark case, the bubble rising process is accompanied with interface deformation subjected to gravity force, viscosity, and surface tension, and it is a test to the algorithms. We applied KGC-MSPH to simulate the bubble rising process, and the results are compared to those in previous literature (Sussman et al., 1994) obtained with the level set method to prove the effectiveness of KGC-MSPH. The initial condition of this case is shown in Figure 8, and the bubble with radius
The timestep is set as
FIGURE 9. Snapshots of bubble rising. A MSPH-KGC solution with resolution of 192 × 320, B MSPH-KGC solution with resolution of 384 × 640, C Level set solution in (Sussman et al., 1994).
5 FCI simulation and mechanism analysis
Considering economy, safety, and reliability as well as engineering technology foundation, various countries have gradually agreed on the design scheme of the SFR. The core is made of metal fuel or MOX fuel, and stainless steel is used as the cladding material. Metal-fueled fast reactors are promising because metal fuels have better proliferative properties than MOX fuels, which is an important advantage for fast reactors (Carmack et al., 2009). However, metal uranium fuel has poor irradiation stability, low melting point, and is easy to crystallize with cladding at low temperature (Ogata, 2014). These shortcomings threaten the safety of the reactor core in serious accidents and may lead to CDAs. As an important phenomenon contained in CDAs (Tobita et al., 2016), molten fuel is fragmented and solidified into debris surrounding by the coolant in the FCI. The debris is relocated on the lower head or the core catcher. The fragmentation characteristics of the FCI significantly affect the heat transfer deterioration in core as well as cooling and re-criticality in the lower head and core catcher. The FCI is numerically studied with the developed KGC-MSPH method in this work. The fuel material is uranium, and the coolant is sodium. The interactions between the fuel, which is coated with melted cladding material, and the coolant were simulated as well. In practice, such mixed situations may be more common and equally valuable; however, they are rarely studied in the published literatures.
Regardless of heat transfer and phase transition, we assume that uranium, stainless steel, and sodium remain liquid and interact with each other. The hydrodynamic fragmentation in the FCI is our focus. The sodium pool is placed in a 2D Cartesian coordinate system with a width of 0.6
5.1 Breakup behavior
Figures 10, 11, 12 show the images of typical moments in the aforementioned three FCI processes, respectively. In order to clearly present the details of fragment distribution, we show uranium particles in red, stainless steel particles in green, and hide sodium particles. The simulated processes ended before liquid uranium hit the bottom of the sodium pool, which took about 0.57 s in all three cases. The initial layout for each case is shown in subfigure (a) of the series. In the process of direct interaction between uranium and sodium, as shown in Figure 10, the initially stationary uranium droplet began to slowly accelerate downward under gravity, and the circular droplet gradually developed into a crescent-shape droplet. Before 0.3 s, the droplet basically maintained good integrity. After that, the liquid sodium beneath the uranium droplet quickly flowed over the lower surface and carried a few small fragments away from the main body, rolling toward the low-pressure region behind the droplet and forming two vortexes, as shown in Figures 10D,E. As the falling speed of molten uranium increased, a large amount of uranium was elongated and stripped at the edge and is continuously taken away by the mainstream. The trailing vortices formed on both sides make the fragments more fully broken and dispersed in space. This is the typical phenomenon of boundary layer stripping. In addition, the main uranium body was obviously affected by Kelvin–Helmholtz (K–H) instability due to the relative velocity parallel to the interface and R–T instability due to gravity, both of which appeared later than the boundary layer stripping. Figure 13 shows the local magnified image at 0.57 s. The three hydraulic phenomena which are mentioned lead to the fragmentation which occurred simultaneously at that moment. They are in agreement with the discussion given by Nishimura et al. (2010) in form of a jet penetrating a surrounding fluid. Gray sodium particles are also shown in the magnified image included in Figure 13. We can observe that the complex interface can be clearly captured and particles near the interface with high density ratio are evenly distributed and accurately described. It proves the effectiveness of the KGC-MSPH method in solving FCI problems.
FIGURE 11. Initial setup and images in the interaction between U coated with Stainless steel film with thickness of 0.01 m and Na.
FIGURE 12. Initial setup and images in the interaction between U coated with Stainless steel film with thickness of 0.02 m and Na.
In the interactions between the uranium droplet coated with the stainless steel film and sodium coolant, the process can also be divided into two stages according to the integrity of the droplet. As shown in Figures 11, 12, the shape change of the uranium droplet in the first stage (0–0.35 s) is similar to that in the direct interaction and no fragments are generated. As mentioned previously, the dynamic viscosities of uranium and stainless steel are very close, and the density difference is not large, so the stainless steel film prevented the shear force from liquid sodium directly acting on the uranium surface. The isolation from the stainless steel film allowed the uranium droplets to remain unbroken for much longer than that in direct interaction, and the obtained droplet remained crescent-shaped. With falling speed, the lower stainless steel film gradually thinned under the shear forces and accumulated on the upper surface of the droplet. The stainless steel film was gradually elongated with the boundary layer movement and will be separated from the main body. In the later stage (0.35–0.57 s), the uranium at the crescent tips began to detach from the main body with the liquid stainless steel and formed uranium fragments which are adhered to stainless steel. The stainless steel film on the underlying surface of the main uranium body continued to be stretched and remained attached to the surface. The upper surface was always covered with a thicker film of stainless steel.
5.2 Result analysis
It can be observed from the FCI cases that the fragments formed mainly include a main uranium body with the largest mass and a large number of small fragments caused by boundary layer stripping. In order to illustrate the fragment distributions and analyze the influence of the stainless steel film, we made statistics on the total number of fragments and the mass change of the main uranium body. As shown in Figure 14, from the development trend of the total number of fragments, represented by
Therefore, according to the aforementioned simulation results, it can be concluded that the KGC-MSPH method can realize the simulation of multiphase flow with intense interface deformation under a large density ratio. The obtained interface is smooth, and the calculation is stable. In the 2D FCI simulation results, we can clearly observe the effect of boundary layer stripping, R–T instability and K–H instability. Boundary layer stripping is the main reason for the generation of small fragments, while R–T instability and K–H instability mainly cause the deformation of the main body. In addition to the direct interaction between uranium and sodium, we also considered the influence of the stainless steel film. The presence of the stainless steel film has a significant inhibition effect on uranium droplet fragmentation. The thicker the liquid film is, the more obvious the inhibition is, the smaller the number of fragments is, and the larger the size of the main body is. In addition, the obtained fragments of all sizes were adhered to stainless steel or wrapped by a thin stainless steel film. Our further analysis suggests that the hydraulic fragmentation of the molten fuel is impeded with the stainless steel film, and the larger debris produced is more likely to block coolant channels, leading to deterioration in core. On the other hand from the thermal perspective, the thermal conductivity of stainless steel is lower than that of uranium, and the stainless steel coat has a negative effect on the cooling of the molten fuel. The risk of re-criticality may arise, resulting in a pessimistic result. It is adverse to the safety of the reactor.
6 Conclusion
An improved MSPH with KGC is developed in this work to solve the simulation problem of multiphase flow with a large density ratio and drastic interface deformation. The KGC-MSPH is further applied to simulate FCI problems including the U–Na direct interaction and the interactions between uranium coated with stainless steel films of different thickness and sodium. The breakup behaviors, the number of fragments, and the mass of the main uranium body in each case are comparatively studied. The conclusions are drawn as follows:
1) Remarkable performance of KGC-MSPH is obtained; the unstable and mixed-interface problems are significantly solved. The capability of KGC-MSPH was validated by simulating the deformation of square droplet, R-T instability, and bubble rising in water.
2) Smoother interfaces can be obtained by considering the repulsive force model. The coefficient of this model applicable to this improved method is suggested to be around 0.01.
3) The breakup behaviors in all three FCI cases are similar, which are mainly affected by three hydraulic factors. Boundary layer stripping is the cause of the formation of a large number of small fragments. R–T instability and K–H instability act on the main body to deform the interface.
4) The stainless steel film can inhibit the breakup of the uranium droplet so that the integrity of the droplet can be maintained for a longer time, the number of fragments formed is less, and the main body size is larger. The thicker the liquid film is, the more obvious the inhibition effect is. The formed fragments and the main body are adhered to liquid stainless steel. The presence of the stainless steel film is suggested to be adverse to the safety of the reactor.
There are still some deficiencies in the simulation of FCI problems, which need to be improved in the future. The spatial scale of the sodium pool is limited, resulting in a short simulation process and the model is 2D. It can be further expanded in the computational domain scale and spatial dimension by solving the problem of computational cost. The thermal hydraulics behaviors closer to the actual situation can be simulated by further considering the thermodynamic model. With continuous development, the improved MSPH is expected to be a powerful tool for nuclear safety analysis and thermohydraulic calculation.
Data availability statement
The raw data supporting the conclusions of this article will be made available by the authors, without undue reservation.
Author contributions
FW carried out the method research and developed the code, performed the simulations, analyzed results, and wrote the manuscript. Z-GZ supervised the research and revised the manuscript. QW assisted in analyzing the results and writing the manuscript.
Funding
This research was supported by Projects of the National Natural Science Foundation of China [grant numbers 52176151 and 51476040], CNNC’s Pilot-innovation Research Project, and Fundamental Research Funds for the Central Universities of China [grant number 3072022TS1503].
Acknowledgments
The authors thank the projects for the financial support.
Conflict of interest
The authors declare that the research was conducted in the absence of any commercial or financial relationships that could be construed as a potential conflict of interest.
Publisher’s note
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Nomenclature
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Keywords: smoothed particle hydrodynamics, kernel gradient correction, fuel-coolant interaction, multiphase flow, large density ratio, fragmentation
Citation: Wang F, Zhang Z-G and Wu Q (2023) An improved multiphase SPH algorithm with kernel gradient correction for modelling fuel–coolant interaction. Front. Energy Res. 11:1041986. doi: 10.3389/fenrg.2023.1041986
Received: 12 September 2022; Accepted: 02 January 2023;
Published: 08 February 2023.
Edited by:
Songbai Cheng, Sun Yat-sen University, ChinaReviewed by:
Zidi Wang, Japan Atomic Energy Agency, JapanXiaoxing Liu, Sun Yat-sen University, China
Copyright © 2023 Wang, Zhang and Wu. This is an open-access article distributed under the terms of the Creative Commons Attribution License (CC BY). The use, distribution or reproduction in other forums is permitted, provided the original author(s) and the copyright owner(s) are credited and that the original publication in this journal is cited, in accordance with accepted academic practice. No use, distribution or reproduction is permitted which does not comply with these terms.
*Correspondence: Zhi-Gang Zhang, emdfemhhbmdAaHJiZXUuZWR1LmNu