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ORIGINAL RESEARCH article

Front. Phys., 11 September 2023
Sec. Mathematical Physics

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

  • 1Faculty of Science, Al Balqa Applied University, Al-Salt, Jordan
  • 2Faculty of Science, Zarqa University, Zarqa, Jordan

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 P239u. 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 as

1vϕr,tt=sr,tΣarϕr,t.Jr,t,

where υ is the neutron velocity, ϕr,t is the neutron flux, sr,t is the neutron source term, Σa is an absorption macroscopic cross section, and r is the position vector at the time t.

The continuity equation involves both neutron current Jr,t and neutron flux ϕr,t, where the relationship between current and the flux can be shown using Fick’s law, which is given in the following mathematical equation:

Jr,t=Dϕr,t,

where D 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:

1vϕr,tt=sr,tΣarϕr,t+D2ϕr,t,

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:

D2ϕr,θ+υfaϕr,θ=0.(1)

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 [521]. To the best of our knowledge, the residual power series method (RPSM) [2129], 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 [2129]. 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:

Dtδft=1Γmδ0ttζmδ1fmζdζ,m1<δ<m,0ζ<t,fmt,δ=m,(2)

where δ(m,m1, Dtδ is the CFD operator and Γ is the gamma function.

Moreover, the numerical results in this study are contrasted using pure P239u for the first time in studying spherical and hemispherical neutron diffusion equations, whereas the previous works in history studied pure U238.

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.

The basic definition in addition to the basic theories of RPSM and its applicability to different types of differential equations is given in [2129]. For the convenience of the reader, we will introduce a review of the RPSM by clarifying the following algorithm on an ordinary differential equation:

(1) Express the nth-order ordinary differential equation in the following general form:

xx0nϕnx=Nxϕ,(3)

subject to the initial conditions

ϕkx0=λk,k=0,1,2,,n1,(4)

where ϕ is an unknown function of x on an open interval I containing x0 and Nx is a nonlinear differential operator of order jn1, and its coefficients are polynomials.

(2) If x0 is a regular point for Eq. 3, assume the solution has a power series expansion:

ϕx=k=0ckxx0k,(5)

whereas if x0 is a singular point for Eq. 3, assume the solution has the following expansion (this is the new case that the RPSM did not address):

ϕx=i=0ckxx0k+δ,c00.(6)

(3) Define the residual functions as follows:

Resx=xx0nϕnxNxϕ.(7)

Indeed, Resx=0, for every xI and so djdxjResx=0,j=0,1,2, at every interior point of I.

(4) Substitute the expansions (5) and (6) of ϕx into Eq. 7 to obtain, respectively, the following expansions:

Resx=k=nckk!kn!xx0kNxk=0ckxx0k,(8)
Resx=k=0ckΓk+δ+1Γk+δn+1xx0k+δNxk=0ckxx0k,(9)

where Γ is the gamma function.

(5) In the singular point case, we need to find the value of δ0. Therefore, we find the CFD of order δ for the residual function in Eq. 9 as follows:

Dx0δResx=k=0ckΓk+δ+12Γk+δn+1k!xx0kDx0δNxk=0ckxx0k,(10)

where Dx0δ is the CFD of order δ0, which has the following two properties: 1) Dx0δa=0,a is a constant 2) Dx0δxx0γ=Γγ+1Γγδ+1xx0γδ.

(6) Since the CFD of a constant is 0, the value of δ is the solution of the following indicial equation:

Dx0δResx0=0.(11)

Since Resx=0 and Dx0δResx=0 for all x in the interior of I, the following equations are true:

didxiResx=0,i=0,1,2,,(12)
didxiDx0δResx=0,i=0,1,2,.(13)

(7) If x0 is a regular point for Eq. 3, then ck=λk,k=0,1,2,,n1, and ck for k=n,n+1,n+2,, can be determined by solving the following algebraic equations, sequentially:

dkndxknResx0=0,k=n,n+1,n+2,,(14)

whereas if x0 is a singular point for Eq. 3, then c00 is arbitrary and can be determined later by the given initial conditions, and ck for k=1,2,3, can be specified by solving the following algebraic equations, sequentially:

dkdxkDx0δResx0=0,k=1,2,3,.(15)

(8) Replace the values obtained for ck, k=0,1,2,m with their place in the expanded series of ϕx to obtain the mth approximate solution to Eq. 3.

(9) If there is a pattern in the coefficients of the series in terms of some well-known elementary functions, then we have the exact solution ϕx.

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 a. The spherical symmetry of the system implies that the flux is a function of r only. The time-independent diffusion Eq. 1 can thus be written as

2ϕr+B2ϕr=0,(16)

where

B2=υfaD(17)

is the buckling of the reactor. Substituting the Laplacian in spherical coordinates and using x=Br, we obtain

x2d2ϕxdx2+2xdϕxdx+x2ϕx=0.(18)

To solve Eq. 18 using RPSM, we assume that the solution has a fractional power series representation at x=0 as follows:

ϕx=n=0cnxn+δ,c00.(19)

Define the residual function of Eq. 18 as

Resx=x2d2ϕxdx2+2xdϕxdx+x2ϕx.(20)

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

Resx=n=0n+δn+δ1cnxn+δ+n=02n+δcnxn+δ+n=0cnxn+δ+2.(21)

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

Dx0δResx=n=0n+δn+δ1Γn+δ+1n!cnxn+n=02n+δΓn+δ+1n!cnxn+n=0Γn+δ+3n+2!cnxn+2.(22)

The solution of the indicial equations Dx0δRes0=0 gives δ=0. Thus, Eq. 22 becomes

Dx0δResx=Resx=n=0nn1cnxn+n=02ncnxn+n=0cnxn+2.(23)

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

djResxdxj=n=1n2n1cnxn1+n=12n2cnxn1+n=0n+2cnxn+1,j=1,n=2n2n12cnxn2+n=22n2n1cnxn2+n=0n+2n+1cnxn,j=2,n=jnn1n!nj!cnxnj+n=j2nn!nj!cnxnj+n=j2n+2!cnnj+2!xnj+2,j=3,4,.(24)

According to step (9) in Subsection 2.1, the solution of the algebraic equations

djResxdxjx=0=0,j=1,2,(25)

can be summarized in Table 1.

TABLE 1
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TABLE 1. Some values of the coefficients of the expansion (19).

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:

cn=1n2c0n+1!,n=0,2,4,6,,0,n=1,3,5,.(26)

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

ϕx=n=01nc02n+1!x2n=c0xsinx.(27)

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

ϕBr=c0sinBrBr.(28)

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 r and θ. Therefore, the time-independent diffusion Eq. 1 can be expressed, by writing the Laplacian in the spherical coordinates and using μ=cosθ, as follows:

r22ϕr,μr2+2rϕr,μr+μ1μ2ϕr,μμ+B2ϕr,μ=0,(29)

where the buckling B2 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

ϕr,μ=Rrψμ.(30)

We obtain the eigenvalue equations as follows:

r2d2Rrdr2+2rdRrdr+B2r2mm+1Rr=0,(31)
ddμ1μ2dψμdμ+mm+1ψμ=0.(32)

To solve the radial part using RPSM, we first, for simplicity, consider x=Br and rewrite Eq. 31 as

x2d2Rxdx2+2xdRxdx+x2mm+1Rx=0,(33)

and we assume the solution has a power series representation at x=0,

Rx=n=0cnxn+δ.(34)

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

Resx=x2d2Rxdx2+2xdRxdx+x2Rxmm+1Rx.(35)

If we substitute Eq. 34 into the residual function (35), then we obtain the following series function:

Resx=n=0n+δn+δ1cnxn+δ+n=02n+δcnxn+δ+n=2cn2xn+δmm+1n=0cnxn+δ,(36)

and so, the CFD of the residual function of order δ in Eq. 36 has the following expansion:

Dx0δResx=n=0n+δn+δ1Γn+δ+1n!cnxn+n=02n+δcnΓn+δ+1n!xn+n=2Γn+δ+1n!cn2xnmm+1n=0Γn+δ+1n!cnxn.(37)

Substituting x=0 in Eq. 37 gives the indicial equation of series (34), whose solution is δ=m. Hence, the residual function in Eq. 37 can be rewritten as

Dx0mResx=n=0n+mn+m1n+m!n!cnxn+n=02n+mn+m!n!cnxn+n=2n+m!n!cn2xnmm+1n=0n+m!n!cnxn.(38)

Following the same manner as in Section 2.2, if we apply the sequential operator djdxi, j=1,2,3, on both sides of Eq. 38, we obtain

djDx0mResxdxj=n=1n+m!n1!n2m+n+1cnxn1+n=2n+m!n1!cn2xn1,j=1,n=2n+m!n2!n2m+n+1cn+cn2xn2,j=2,n=jn+m!nj!n2m+n+1cn+cn2xnj,j=3,4,.(39)

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

TABLE 2
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TABLE 2. Some values of the coefficients of the expansion (34).

It is clear that there is a pattern in the coefficients of our series. So, the nth coefficient, cn, has a general form as follows:

cn=1n2c024n2m+32m+52m+n+1,n=0,2,4,6,,0,n=1,3,5,,(40)

which can be reformulated as follows:

cn=c01n2m+1!m+n!m!n!2m+2n+1!,m0,1,2,3,,n=0,1,2,3,.(41)

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

RmBr=n=0Cmn1n2m+1!m+n!m!n!2m+2n+1!Br2n+m.(42)

Now, to solve the angular part, which is a Legendre equation, we construct the residual function of Eq. 32 as

Resμ=d2ψμdμ2μ2d2ψμdμ22μdψμdμ+mm+1ψμ,(43)

and since μ=0 is a regular point of Eq. 32, we assume the solution of the following expansion:

ψμ=n=0cnμn.(44)

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

Resμ=n=2nn1cnμn2n=2nn1cnμnn=12ncnμn+mm+1n=0cnμn.(45)

Applying the differential operator djdxi, j=0,1,2,3, on both sides of Eq. 45 gives

djResxdxj=n=0n+2n+1cn+2+mm+1cnμnn=2nn1cnμnn=12ncnμn,j=0,n=1nn+2n+1cn+2+mm+12ncnμn1n=2n2n1cnμn1,j=1,n=2nn1n+2n+1cn+2+mnm+n+1cnμn2,j=2,n=jn!nj!n+2n+1cn+2+mnm+n+1cnμnj,j=3,4,.(46)

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

TABLE 3
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TABLE 3. Some values of the coefficients of expansion (44).

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:

ψm0μ=cm01+m2!2m!n=1m21nm+2n!μ2nm2n!m2+n!2n!,m=2,4,6,,ψm1μ=cm1x+m12!2m!n=1m121nm+2n!μ2n+1m12n!m12+n!2n+1!,m=1,3,5,.(47)

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

ψmμ=cmPmμ=cm12mn=0m/21n2m2n!μm2nn!mn!m2n!.(48)

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

ψmμ=cmPmμ=cm12mm!dmdμmμ21m.(49)

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

ϕr,μ=m=0ϕmr,μ=m=0AmRmrPmμ.(50)

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 ac 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 ac+2D. 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 n.ϕr,μ=grϕr,μ.

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:

n.ϕr,μ=grϕr,μ,(51)

where gr varies over the surface, and this RBC is reported in previous works [34, 35].

The RBC on the curved surface where r=a will be

ϕr,μxr=a=g1ϕa,μ.(52)

However, RBC on the flat surface will be

ϕr,μxμ=0=g2ϕr,0,(53)

where g1=12D,g2=ga/b2D, where the values of g change from 0 to 1, and the reactor geometry changes from spherical (g= 0) to hemispherical (g= 1) geometry as mentioned in [34, 35].

Applying RBC on the flat surface in Eq. 50 yields

1rAmRmBrPm0=g2AmRmBrPm0.(54)

Using the following recurrence relationships of RnBr:

R2m+1Brr=BR2m+2Br4m+54m+3+BR2mBr,m+1BrRmBr+RmBrB=2m+1Rm1Br,(55)

and some Legendre polynomials properties, we obtain the following relationship:

B2m+1A2m+12mB4m+14m1A2m1=g22m+1A2n.(56)

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

A2m+1=k=0nγmkA2k,(57)

where

γmk=2m2k1!!4k+12k!!2m+14m+1g2B,(58)

as reported in [ 36].

Similarly, applying the RBC on the curved surface, we obtain

m=0AmRBaPmμ=g1m=0AmRBaPmμ,(59)

or it can be written as

m=0AmfmPmμ=0,(60)

where fm isgivenby

fm=ma+g1RmBaB2m+3Rm+1Ba.(61)

Following [35], we obtain

m=0M^mkA2m=0,k=0,1,2,3,(62)

where

M^mk=β2m,kf2m+l=mβ2l+1,kf2l+1γl,m,(63)

and

βmk=2k+101PmμPk2μ1dμ.(64)

The alternating method of βmk is

βmk=Pmμk,(65)

where μk=coskπ/2N, which is used in these calculations.

3 Numerical results

The numerical data of neutrons diffusing in pure P239u are taken from [36], which are shown in Table 4.

TABLE 4
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TABLE 4. Pure P239u cross sections.

The important diffusion constant and buckling are

D=13Σf+Σs+Σγ=1.021241834cm,B=ʋΣfΣf+ΣγD=0.357553294cm1.

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 ac 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 (ac +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 C++ computer code based on Eq. 28 has been written to find the first root of Eq. 28. The value of r at which the flux is 0 is ac,ZF=8.7864 cm. Since the flux is assumed to converge at ac+2D using EBC, then ac,EBC=8.7864. These results are tabulated in Table 5.

TABLE 5
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TABLE 5. Critical radius ac (in cm) for pure P239u for a sphere and hemisphere using different boundary conditions: ZFBC, EBC, and RBC.

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 RnBr of the radial part. The unique available case is for m=1. So Eq. 50 will reduce to the following form:

ϕr,μ=A1R1Brψ1μ=m=0cm1n3!m+1Br1+2m3+2m!μ.(66)

The critical radii in pure P239u that are calculated using the C++ 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 as

m=0NM^mkA2m=0,(67)

where

M^mk=β2m,kf2m+l=nNβ2l+1,kf2l+1γl,m.(68)

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

ϕr,μ=m=02N+1ϕmr,μ=m=02N+1AmRmrψmμ.(69)

A third computer code has been used to calculate the critical radius using RBC. The code calculates the determinant of M^nk. The value of a affects the determinant through the parameters fn (Eq. 61). As a increases, the value of the determinant will change its sign. On the other hand, the calculated ac depends on the value of the interaction parameter g through γnk (Eq. 58). Hence, the results for the sphere and the infinitely separated hemispheres are obtained by using g=0 and g=1, respectively.

The determination of the critical dimension depends on the cut-off value N, where the number of terms will be 2N+2, and the value of the critical dimension with the number of terms is given in Table 6.

TABLE 6
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TABLE 6. Convergence of the critical radius ac (in cm) for the hemisphere using RBC.

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 g on determining the critical radius is clarified in Table 7, where the cut-off value N=10 and the number of terms (22) are considered.

TABLE 7
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TABLE 7. Variation in the critical radius ac with the interaction parameter g. N=10 (22 terms).

The reactor is a sphere when the interaction parameter g=0, whereas it is a hemisphere when the interaction parameter g=1, 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

ϕr,μ=m=02N+1A2mR2mBrψ2mμ+A2m+1R2m+1Brψ2m+1μ.(70)

For computational calculation purpose, this equation can be expressed as

ϕ¯r,μ=m=0NA2mR2mBrPψ2mμ+l=mNγl,nR2m+1Brψ2m+1μ.(71)

The amplitudes A2m in Eq. 62 are needed to be written in the form

n=0NM^nkA2m=M^0kA0,(72)

where A1 has been normalized to unity. So A0 =1γ00, and the flux values are normalized to the averaged flux.

ϕ¯=0a01r2ϕr,μdμdr0a01r2dμdr.(73)

The value of the average flux is

ϕ¯=3a30ar2dr01ϕr,μdμ.(74)

Based on these data, the averaged flux calculated using the C++ code was determined to be 0.756965. The variation in the flux at θ=π/4 with r changes from zero, and the critical radius is given in Table 8 for different values of N (different number of terms).

TABLE 8
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TABLE 8. Flux variation across the critical hemisphere at θ=π/4

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 N=1,2,3,4, and 30).

FIGURE 1
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FIGURE 1. Angular distribution over the curved surface.

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 P239u, is expected which is the same as in using the homotopy perturbation method in solving the neutron diffusion equation where neutrons diffuse in the U235 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
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FIGURE 2. Flux distribution across the core of a bare hemisphere at different angles N=1022terms

As shown in Figure 2, it is noted that the radial flux does not decrease when r 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.

TABLE 9
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TABLE 9. Flux variation across the critical hemisphere at different values of θ. N=10 (22 terms).

FIGURE 3
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FIGURE 3. Flux distribution across the core of a bare hemisphere as a function of r and θ. N=10(22 terms).

Furthermore, a three-dimensional plot of the flux distribution across the core of a bare hemisphere as a function of r and θ 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 P239u in this paper are studied using RPSM for the first time and the neutrons diffusing in U235 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 C++ 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 [3741].

Data availability statement

The original contributions presented in the study are included in the article/Supplementary Material; further inquiries can be directed to the corresponding author.

Author contributions

All authors listed have made a substantial, direct, and intellectual contribution to the work and approved it for publication.

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

All claims expressed in this article are solely those of the authors and do not necessarily represent those of their affiliated organizations, or those of the publisher, the editors, and the reviewers. Any product that may be evaluated in this article, or claim that may be made by its manufacturer, is not guaranteed or endorsed by the publisher.

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Keywords: neutron diffusion, power series, radial flux, radiation boundary condition, nuclear reactor physics

Citation: El-Ajou A, Shqair M, Ghabar I, Burqan A and Saadeh R (2023) A solution for the neutron diffusion equation in the spherical and hemispherical reactors using the residual power series. Front. Phys. 11:1229142. doi: 10.3389/fphy.2023.1229142

Received: 25 May 2023; Accepted: 23 August 2023;
Published: 11 September 2023.

Edited by:

Rami Ahmad El-Nabulsi, Chiang Mai University, Thailand

Reviewed by:

Marwan Alquran, Jordan University of Science and Technology, Jordan
Yusif Gasimov, Azerbaijan University, Azerbaijan

Copyright © 2023 El-Ajou, Shqair, Ghabar, Burqan and Saadeh. 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: Rania Saadeh, cnNhYWRlaEB6dS5lZHUuam8=

Disclaimer: All claims expressed in this article are solely those of the authors and do not necessarily represent those of their affiliated organizations, or those of the publisher, the editors and the reviewers. Any product that may be evaluated in this article or claim that may be made by its manufacturer is not guaranteed or endorsed by the publisher.