A solution for the neutron diffusion equation in the spherical and hemispherical reactors using the residual power series

Abstract

A novel analytical solution to the neutron diffusion equation is proposed in this study using the residual power series approach for both spherical and hemispherical fissile material reactors. Various boundary conditions are investigated, including zero flux on the boundary, zero flux on the extrapolated boundary distance, and the radiation boundary condition (RBC). The study also shows how two hemispheres with opposing flat faces interact. We give numerical results for the same energy neutrons diffused in pure . By qualitative comparison with the homotopy perturbation method and Bessel function-based solutions, the residual power series method (RPSM) presents accurate series solutions that converge to the exact solutions, as shown in this study. Moreover, numerical results were shown to be improved by the computer implementation of the analytic solutions.

1 Introduction

Modern physics is taken into consideration after classical physics failed to explain various phenomena, and many branches of modern physics developed, including nuclear physics. To perform nuclear fission in a nuclear reactor, it is essential to have a neutron in the thermal state to break through the nucleus, as each fission produces more than one neutron, leading to a new reaction where a chain reaction is created [1].

The continuity equation, known as the time-dependent transfer equation, expresses the distribution of neutrons in the reactor, which is given aswhere is the neutron velocity, is the neutron flux, is the neutron source term, is an absorption macroscopic cross section, and is the position vector at the time .

The continuity equation involves both neutron current and neutron flux , where the relationship between current and the flux can be shown using Fick’s law, which is given in the following mathematical equation:where is the diffusion coefficient.

By applying Fick’s law, the time-dependent transport equation can be simplified to the following time-dependent neutron diffusion equation:whose solution is considered very important in studying the behavior of neutrons in reactors [2, 3].

The stability of the nuclear reactor has been studied in detail in the past [4]. The condition of criticality in a nuclear reactor is essential to ensure its stability, as the number of neutrons in the reactor must be constant at any time. The flow in the critical state must be time-independent, which can be mathematically expressed using a time-independent diffusion equation as follows:

Various techniques, analytical and numerical, have been employed to solve the neutron diffusion equation throughout the past few decades, such as the homotopy perturbation method, the Laplace transform process, and the Galerkin method with B-splines [5–21]. To the best of our knowledge, the residual power series method (RPSM) [21–29], an analytical technique, has never been used to handle issues relating to the neutron diffusion equation.

RPSM is a relatively new technique that provides exact and approximate analytical solutions in the series form to many differential and integrodifferential equations of integer and fractional orders [21–29]. The idea of the RPSM is based on using the residual function and the derivative operator concepts in determining the coefficients of the solution, which is assumed to be in a power series form. In RPSM, it is usual to use a classical derivative operator to determine the coefficients of a power series solution if the differential equation is of integer order. However, a fractional derivative operator is used to determine the coefficients if the differential equation is of fractional order.

Later, we will rewrite Eq. 1 using spherical coordinates in spherical and hemispherical reactors, which gives rise to single equations. This work aims to adapt and modify RPSM to solve Eq. 1 after being formulated in spherical coordinates. This modification is a regeneration of RPSM and is presented for the first time in this work. This modification relies on using a fractional derivative operator, such as the Caputo fractional derivative (CFD) [30, 31] or the conformable fractional derivative [21, 32], in differential equations of the integer order. Since the equations to be solved are singular, we impose the solution in a Frobenius series form. Therefore, the new modified method can be considered an alternative method to the Frobenius method in determining the power series solution coefficients.

In fact, several types of fractional derivative operators can be used in our hypothetical modification of the RPSM, such as the CFD operator, the Riemann–Liouville fractional derivative operator [33], and the conformable fractional derivative operator. The CFD is employed in the modified method without bias or preference to determine the Frobenius series coefficients. The CFD operator is defined using the following formula:where , is the CFD operator and is the gamma function.

Moreover, the numerical results in this study are contrasted using pure for the first time in studying spherical and hemispherical neutron diffusion equations, whereas the previous works in history studied pure .

The following section presents the methodology of the RPSM and its application to spheres and hemispheres. The radiation boundary condition is also covered in depth to set the stage for the computations. Section 3 presents numerical results for the flux distribution in the studied nuclear reactors and critical radius calculations. The associated technical problems encountered throughout the computations are presented, along with the corresponding solutions.

2 Theory

2.1 The basic idea of the RPSM

RPSM is a technique to find the power series solution coefficients without having a recurrence relation. Indeed, the coefficients of the power series are calculated by the concept of residual error through a sequence of algebraic equations, and in the end, a truncated series solution (approximate solution) is obtained. The major merit of RPSM is that it can be implemented to the problem directly without linearization, perturbation, or discretization and without any transformation by selecting appropriate initial conditions.

Most of the problems resolved using RPSM were to provide series solutions about regular points and did not address situations where there are singular points. In this work, we introduce a simple modification to the construction of the RPSM to be able to solve issues containing these types of points.

2.2 Bare sphere

First, the application of RPSM in spherical reactors is studied. We consider first the rather simple example of a bare spherical reactor of radius . The spherical symmetry of the system implies that the flux is a function of only. The time-independent diffusion Eq. 1 can thus be written aswhereis the buckling of the reactor. Substituting the Laplacian in spherical coordinates and using , we obtain

To solve Eq. 18 using RPSM, we assume that the solution has a fractional power series representation at as follows:

Define the residual function of Eq. 18 as

Substitute Eq. 19 into the residual function (20), we obtain the following series:

According to Eq. 10, the CFD of the residual function in Eq. 21 will be as

The solution of the indicial equations gives . Thus, Eq. 22 becomes

Thus, the th derivative of the residual function has the following general form:

According to step (9) in Subsection 2.1, the solution of the algebraic equationscan be summarized in Table 1.

If we continue in the same manner, then we conclude that the general form of the coefficients in series (19) will be in the following form:

Therefore, the solution for Eq. 18 has the following exact solution:

Consequently, the final solution for Eq. 16, in a closed form, is given by

This flux must satisfy the relevant boundary conditions.

2.3 Hemispherical reactor

In this subsection, we will consider the hemispherical reactor. This case is more complicated because the flux is a function in two variables and . Therefore, the time-independent diffusion Eq. 1 can be expressed, by writing the Laplacian in the spherical coordinates and using , as follows:where the buckling is again given by Eq. 17.

2.3.1 Solution by the separation of variables and residual power series method

Applying the separation of variables, we obtain

We obtain the eigenvalue equations as follows:

To solve the radial part using RPSM, we first, for simplicity, consider and rewrite Eq. 31 asand we assume the solution has a power series representation at ,

The residual function of Eq. 33 has the following form:

If we substitute Eq. 34 into the residual function (35), then we obtain the following series function:and so, the CFD of the residual function of order in Eq. 36 has the following expansion:

Substituting in Eq. 37 gives the indicial equation of series (34), whose solution is . Hence, the residual function in Eq. 37 can be rewritten as

Following the same manner as in Section 2.2, if we apply the sequential operator , on both sides of Eq. 38, we obtain

Consequently, the first few coefficients of the series in Eq. 34 are given in Table 2.

It is clear that there is a pattern in the coefficients of our series. So, the th coefficient, , has a general form as follows:which can be reformulated as follows:

Therefore, the eigensolutions to the Sturm–Liouville equation in Eq. 31 appear in the following series:

Now, to solve the angular part, which is a Legendre equation, we construct the residual function of Eq. 32 asand since is a regular point of Eq. 32, we assume the solution of the following expansion:

Substitute Eq. 44 into Eq. 43, and we obtain

Applying the differential operator , on both sides of Eq. 45 gives

Thus, the first few coefficients of the series in Eq. 44 are given in Table 3.

Note that there are two linearly independent solutions one of them is an infinite series and the other is a polynomial of degree m. If m is an even number, then the solution that contains terms of even exponents will be the polynomial whereas the solution that contains terms of odd exponents will be infinite series and vice versa if m is an odd number. Anyway, we can keep track of the pattern in the coefficients and write the solutions as follows:

Legendre was able to combine both solutions in a single format, regardless of whether the number was odd or even as

By using Rodrigues’s formula for the Legendre polynomials, the solution can be expressed as follows:

Therefore, the general solution for Eq. 29 can be expressed as

2.4 The radiation boundary condition

Although the choice of suitable boundary conditions in solving the neutron diffusion equation is at the core of the nuclear reactor physicist mission, here, we will apply three boundary conditions, namely, zero flux boundary condition (ZFBC), extrapolated boundary condition (EBC), and radiation boundary condition (RBC). These boundary conditions will be applied on both spherical and hemispherical reactors.

ZFBC cures about the point at the surface of the reactor that the flux is 0, and for more reality, the flux will vanish at a point less than that point which is called extrapolated distance . To be more accurate, especially for the hemisphere, the mixed boundary condition gives the closest results when comparing to the benchmark; this boundary condition is called RBC

The use of the application of RBC on the solution of the hemispherical reactor using RPSM based on the separation of variable techniques can be performed as follows:where varies over the surface, and this RBC is reported in previous works [34, 35].

The RBC on the curved surface where will be

However, RBC on the flat surface will bewhere where the values of g change from 0 to 1, and the reactor geometry changes from spherical (0) to hemispherical ( 1) geometry as mentioned in [34, 35].

Applying RBC on the flat surface in Eq. 50 yields

Using the following recurrence relationships of :and some Legendre polynomials properties, we obtain the following relationship:

We can use the previous result to write the odd term amplitude in terms of the even term amplitude aswhere

as reported in [ 36].

Similarly, applying the RBC on the curved surface, we obtainor it can be written aswhere

Following [35], we obtainwhereand

The alternating method of iswhere , which is used in these calculations.

3 Numerical results

The numerical data of neutrons diffusing in pure are taken from [36], which are shown in Table 4.

The important diffusion constant and buckling are

Depending on these data, to calculate the flux, applying different boundary conditions, to find the critical radii, and to study the flux distribution for both spherical and hemispherical reactors,, this work has been compared with benchmark calculations [34].

3.1 Critical radius calculations

The critical radius is the dimension of the reactor determined as the flux vanished. The determination of the critical radius depends on the boundary conditions, and the simplest way of calculating it is by using ZFBC, where the flux vanishes. In real reactors, an extrapolated distance must be considered ( +2D) at which the value of the flux is 0; this boundary condition is the EBC. The use of ZFBC and EBC is suitable for sphere, cylinder, and slab reactors where there is high symmetry, but for more complicated reactors like hemispherical and cone reactors, we need to use the RBC.

The first case we will study is the spherical reactor. Here, the critical radius using ZFBC and EBC is considered, and the results are compared with RBC. A computer code based on Eq. 28 has been written to find the first root of Eq. 28. The value of at which the flux is 0 is cm. Since the flux is assumed to converge at using EBC, then . These results are tabulated in Table 5.

After taking the bare sphere, the hemispherical reactor is considered, and the neutron flux using ZFBC will vanish on the flat surface (µ = 0). Using the Legendre polynomial properties, the even amplitudes must be equal to 0, and on the curved surface, we need to find the first zero of the solution of the radial part. The unique available case is for . So Eq. 50 will reduce to the following form:

The critical radii in pure that are calculated using the code depending on Eq. 59 are tabulated in Table 5.

Unlike the spherical reactor, applying RBC is essential for the hemispherical reactor.

The calculation of the critical dimension using RBC is illustrated in the following equation, and the infinite summation in Eq. 62 will be cut off to the value N, where the dimension of the matrix is finite, and rewritten aswhere

This simplification is an important numerical calculation to make cut-off limit value N. Then, the flux in Eq. 50 will be simplified to

A third computer code has been used to calculate the critical radius using RBC. The code calculates the determinant of . The value of a affects the determinant through the parameters (Eq. 61). As increases, the value of the determinant will change its sign. On the other hand, the calculated depends on the value of the interaction parameter g through (Eq. 58). Hence, the results for the sphere and the infinitely separated hemispheres are obtained by using and , respectively.

The determination of the critical dimension depends on the cut-off value N, where the number of terms will be , and the value of the critical dimension with the number of terms is given in Table 6.

The effect of the number of terms is clear; the value of the critical radius is converged by increasing the number of terms. Now, the effect of changing the interaction parameter on determining the critical radius is clarified in Table 7, where the cut-off value and the number of terms (22) are considered.

The reactor is a sphere when the interaction parameter , whereas it is a hemisphere when the interaction parameter , where the values of the critical radii are shown in Table 4 and Table 5, respectively.

3.2 Flux distribution

Now, the flux destruction inside the hemispherical reactor will be considered. It is straightforward that the symmetry of the spherical reactor makes the flux distribution a simple case study in [35], so the flux in Eq. 69 will be written as

For computational calculation purpose, this equation can be expressed as

The amplitudes in Eq. 62 are needed to be written in the formwhere has been normalized to unity. So A₀, and the flux values are normalized to the averaged flux.

The value of the average flux is

Based on these data, the averaged flux calculated using the code was determined to be 0.756965. The variation in the flux at with changes from zero, and the critical radius is given in Table 8 for different values of N (different number of terms).

The convergence of the flux values is clearly given in Table 8.

As shown in Figure 1, the fast convergence of the flux on the curved surface is obtained with the increasing number of terms (for and 30).

FIGURE 1

It is important to clarify, from Figure 1, that the convergence is stable and acceptable, and when the number of terms is 30, the angular flux, which expresses the behavior of neutrons when they are diffusing in pure , is expected which is the same as in using the homotopy perturbation method in solving the neutron diffusion equation where neutrons diffuse in the hemispherical reactor [35].

After studying the effect of the number of terms on the flux, it is taken into consideration at a wide range of angle values in Figure 2.

FIGURE 2

As shown in Figure 2, it is noted that the radial flux does not decrease when increases and the maximum value of the flux shifted with the increase in the angle. One more time, the neutron distribution is in the same manner as in previous work [35].

To clarify the flux behavior in more detail, the flux values for different angles and radii are tabulated in Table 9 and depicted in Figure 3.

FIGURE 3

Furthermore, a three-dimensional plot of the flux distribution across the core of a bare hemisphere as a function of and is shown in Figure 3.

The flux in Table 6 is represented graphically in Figure 3. The data in Figure 1 and Figure 2 are merged in the same figure, where the full neutron behavior is represented; however, this three-dimensional flux representation is not figured out previously for the hemispherical reactor.

Although the neutrons diffusing in pure in this paper are studied using RPSM for the first time and the neutrons diffusing in were previously studied using the homotopy perturbation method [35, 36], it is clear that their behavior is the same.

4 Conclusion

In this article, we introduced the application of RPSM in solving the neutron diffusion equation in hemispherical symmetry. The method is efficient and can present the solution in the form of a rapid series that converge to the exact solution. Two important cases are discussed: the spherical reactor and hemispherical reactor. The results are presented in tables and illustrative figures using codes. To show the validity of the presented method, we made qualitative comparisons between the obtained results using RPSM and those computed using the homotopy perturbation method. The used method and its computational implementation provide superior results when applied to more complex and reflected reactor geometries for one-group problems. It is recommended, however, for future work to further investigate the methodology for two- and multi-group problems.

In future work, we attend to solve more partial differential equations with physical applications, using the proposed method that showed its accuracy in handling similar problems, and further investigation of the convergence-produced series should be the goal of future specialized research [37–41].

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