Where Can I Learn About Neutron Flux in Finite Mediums?

Click For Summary

Discussion Overview

The discussion revolves around the calculation of neutron flux in finite mediums, specifically focusing on point sources within finite spheres and the differences from infinite mediums. Participants explore various equations and boundary conditions relevant to neutron flux, as well as comparisons to infinite sources.

Discussion Character

  • Technical explanation
  • Mathematical reasoning
  • Debate/contested

Main Points Raised

  • One participant presents an equation for neutron flux in a finite sphere and seeks resources for further learning.
  • Another participant claims to have solved the problem independently but expresses uncertainty about the correct form of the hyperbolic sine function in the equation.
  • A participant suggests classic texts on nuclear engineering as potential resources for understanding neutron flux.
  • Discussion includes the importance of boundary conditions in solving the diffusion equation for finite systems compared to infinite systems.
  • One participant shares their detailed work on deriving the neutron flux equation, including boundary conditions and constants.
  • Another participant confirms the correctness of a derived equation and notes the behavior of the sinh function as r approaches zero.
  • A participant raises a related question about deriving solutions for a line source in a finite medium.
  • There is a mention of an additional error in a previous solution regarding the inclusion of a constant.
  • A participant offers a more complete solution and references a specific chapter from a nuclear reactor analysis text that discusses finite reactors and flux profiles.

Areas of Agreement / Disagreement

Participants express varying degrees of certainty regarding the equations and methods for calculating neutron flux in finite mediums. Some participants agree on certain aspects of the solutions, while others raise questions or point out potential errors, indicating that the discussion remains unresolved with multiple competing views.

Contextual Notes

Participants reference specific boundary conditions and mathematical forms that may depend on the definitions used in their texts. There is also mention of the need to consider neutron leakage in finite systems, which complicates the solutions compared to infinite systems.

theCandyman
Messages
397
Reaction score
2
In the text I use for class, the examples and derivations for functions showing the neutron flux at some point, are all about sources within infinite mediums. Now I have a probelm where I must show that neutron flux, for a point source within a finite sphere, is found by the following equation.

<br /> \phi (r)= \frac{S}{4 \pi D sinh \frac{R + d}{L}} \frac{sinh( \frac{R + d - r}{L} ) }{r}<br />

If anyone can tell me where I could learn about flux in finite mediums, I would appreciate it.
 
Last edited:
Engineering news on Phys.org
I believe I have solved this on my own. I found an example dealing with a infinite plane source within a slab.

For reference for anyone else who may have the same question in the future, I will try to compile the answer into this thread later - it is a bit lengthy.

Edit: I am a bit unsure of the hyperbolic sine in the numerator. In the book it is written like this:

sinh \frac{1}{L} (R+d-r)

If that (R+d-r) term is not in the function, I have done the problem icorrectly. Does anyone know which is the correct formula?
 
Last edited:
What text are you using?

Two classic texts are those by John Lamarsh, "Introduction to Nuclear Engineering" and "Nuclear Reactor Theory".

Sinh is appropriate for an infinite planar source in an infinit slab, and I am trying to remember if A sinh (kr)/r or A sin (kr)/r is appropriate for a sphere. Basically, at r=0, the solution must be finite, and the flux is taken as zero at the extrapolated boundary.

Basically, one is solving the diffusion equation in one, two or 3D in a finite system. The complete solution is determined by the boundary conditions. Unlike the inifinite system, where the only loss of neutrons is due to absorption, the finite system must deal with 'leakeage' of neutrons across physical boundaries.

If you write the form of the diffusion equation and the boundary conditions you used, then we can discuss it.
 
Last edited:
I am using the third edition of Introduction to Nuclear Engineering by Lamarsh.

Here's my work:

\phi = A \frac{e^{-\frac{r}{L}}}{r} + C \frac{e^{-\frac{r}{L}}}{r}
The general solution of point source within a medium flux, A and C are constants.

\phi (R+d) = A \frac{e^{-\frac{R+d}{L}}}{R+d} + C \frac{e^{-\frac{R+d}{L}}}{R+d} = 0
Boundary equation.

C = -Ae^{-\frac{2(R+d)}{L}}
Solving for the constant C.

\phi = \frac{A}{r}(e^{-\frac{r}{L}} - e^{(\frac{r}{L}-\frac{2(R+d)}{L})})
Substituting in the value for C.

J = -D \frac{d\phi}{dr}
r^2 J(r) = \frac{DA}{ L}(1 - e^{-\frac{2(R+d)}{L}})
Note: I took the limit as r goes to zero, so e^-(r/L) goes to 1.

\lim_{r\rightarrow 0}r^2 J(r) = \frac{S}{4\pi}
This is the limit for the left hand side of the above.

A = \frac{SL}{4\pi D}(1 - e^{-\frac{2(R+d)}{L}})^{-1}
Solving for constant A.

\phi = \frac{SL}{4\pi D r} \frac{e^{-\frac{r}{L}} - e^{(\frac{r}{L}-\frac{2(R+d)}{L}})}{1 - e^{-\frac{2(R+d)}{L}}}
Equation after substituting in A.

\phi = \frac{SL}{4\pi D r} \frac{e^\frac{R+d-r}{L} - e^{-\frac{R+d-r}{L}}}{e^{\frac{R+d}{L}} - e^{-\frac{R+d}{L}}}
Simplifying by multiplying numerator and denomator by e^[(R+d)/L]

\phi = \frac{SL}{4 \pi D r} \frac{sinh\frac{R+d-r}{L}}{sinh\frac{R+d}{L}}

That is quite a bit of Latex coding, I will be fixing it if I there is a problem.
 
Last edited:
That looks right.

Importantly sinh (kr)/r -> 1 as r -> 0.
 
I have same exercise, but for the line source in a finite medium?
 
I'm assuming you mean an infinite line source and aren't interested in the ends. It will be a very similar derivation, but you will be dealing with polar instead of spherical coordinates.
 
theCandyman...you have an extra L in your solution...
 
This is a more complete solution:
 

Attachments

  • PointSource_Moderator.gif
    PointSource_Moderator.gif
    17.7 KB · Views: 1,476
  • #10
So how would the complete solution change if a second finite moderating sphere surrounds the existing sphere and point source? Thanks in advance.
 
  • #11
Dunderstadt & Hamilton's Nuclear Reactor Analysis Chapter 5 discusses finite reactors. It gives the Geometric Bucking term for a bare sphere as \left(\frac{\pi}{\widetilde{R}}\right)^2 and the flux profile as r^{-1}sin\left(\frac{\pi r}{\widetilde{R}}\right)
 

Similar threads

  • · Replies 1 ·
Replies
1
Views
2K
  • · Replies 2 ·
Replies
2
Views
5K
  • · Replies 3 ·
Replies
3
Views
4K
Replies
4
Views
6K
  • · Replies 4 ·
Replies
4
Views
4K
Replies
1
Views
3K
  • · Replies 4 ·
Replies
4
Views
2K
  • · Replies 3 ·
Replies
3
Views
2K
  • · Replies 2 ·
Replies
2
Views
2K
  • · Replies 16 ·
Replies
16
Views
5K