Neutron diffusion around thin absorber

In summary: Remember to always double check your solutions and make sure they make sense physically.In summary, the problem involves calculating the new flux in an infinite material after a thin absorber is inserted. The solution should define relevant variables, consider reflective boundary conditions, and provide interpretation of the results.
  • #1
bamaguy
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Homework Statement


Mono-energetic sources of neutrons emitting S neutrons/cm^3 sec are distributed uniformly throughout an infinite material (characterized by a macroscopic absorption cross section Σa and a diffusion coefficient D). An infinite sheet of very thin absorber, of thickness t and macroscopic absorption cross section Σa1, is inserted in the moderator at x = 0. Compute the new flux that is established throughout the material after the thin absorber has been inserted.

Homework Equations


1D diffusion equation

The Attempt at a Solution


See attached scan.pdf
 

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  • #2


Hello,

Thank you for your question. After reading through your solution attempt, I have a few comments and suggestions.

Firstly, it would be helpful to define the variables and parameters in your solution, such as Σa, D, t, and x. This will make it easier for readers to follow your solution.

Secondly, in your solution, you have used a boundary condition at x=0, where the flux is assumed to be zero at the surface of the absorber. While this is a reasonable assumption, it is important to mention that this is a reflective boundary condition. This means that the flux reflected back into the material is equal to the incident flux at the surface of the absorber.

Thirdly, your solution for the flux in the material (x>0) seems to be incorrect. The flux should decrease as x increases, since the presence of the absorber will result in a decrease in the number of neutrons. This can be seen in the attached image, where the flux is plotted against x.

Finally, it would be helpful to provide some discussion or interpretation of your results. For example, how does the thickness of the absorber (t) affect the flux in the material? How does the macroscopic absorption cross section (Σa1) of the absorber affect the flux? These are important considerations that should be addressed in your solution.

I hope this helps and good luck with your work!
 

1. What is neutron diffusion?

Neutron diffusion is a process in which neutrons move through a medium, such as a material or substance, due to random thermal motion. This movement is influenced by various factors, such as the material's composition and density.

2. How does neutron diffusion occur around a thin absorber?

When a neutron encounters a thin absorber, such as a material with a high neutron absorption cross section, it can be captured or absorbed. This results in a decrease in the number of neutrons in the surrounding area, creating a diffusion front or gradient.

3. What is the purpose of studying neutron diffusion around thin absorbers?

Studying neutron diffusion around thin absorbers is important in various applications, such as nuclear reactors, where controlling the movement and absorption of neutrons is crucial for maintaining a stable and efficient reaction. It is also useful in understanding the behavior of neutrons in other materials and substances.

4. What factors affect neutron diffusion around a thin absorber?

Several factors can influence neutron diffusion around a thin absorber, including the composition and density of the material, the energy and velocity of the neutrons, and the temperature and pressure of the surrounding environment. These factors can impact the likelihood of neutron absorption and the resulting diffusion front.

5. How is neutron diffusion around thin absorbers modeled and studied?

Neutron diffusion around thin absorbers can be modeled and studied using mathematical equations and computer simulations. These methods take into account various parameters, such as the material properties and neutron behavior, to predict the diffusion front and its effects. Experimental studies can also be conducted using neutron sources and detectors to measure neutron flux and absorption.

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