Is Fission Classified as Capture or Noncapture?

  • Thread starter Thread starter cooper7d7
  • Start date Start date
  • Tags Tags
    Capture Fission
AI Thread Summary
The discussion centers on solving a problem regarding the probability of a 1 MeV neutron slowing to thermal energy in a water/uranium environment. It clarifies that the fission cross-section is considered a part of the total capture, as it represents a loss during the slowing process, despite producing additional fast neutrons. The participants emphasize that fission neutrons cannot be treated as the same as the impacting neutron due to their differing energy levels. The distinction between thermal and fast neutrons is crucial for accurate calculations in neutron behavior. Understanding these concepts is essential for addressing neutron interactions in nuclear physics.
cooper7d7
Messages
4
Reaction score
0
I apologize that me first post is such a silly one.

I am trying to solve problem 1.2 in Stacey. It asks for the probability of a 1 MeV neutron slowing to thermal. I can determine the number of collisions required in the water / uranium environment. But, when I go to select the proper crosssections, I think I should just use scattering but I was wondering if fission is considered capture or noncapture?

Thanks, I really enjoy this forum...

-Will
 
Engineering news on Phys.org
The fission cross-section would be considered capture, e.g. part of the total capture. It represents a loss during the slowing down process, but then it produces 2 or 3 fast neutrons.
 
Ok

Makes sense, I was just thinking that maybe one of the 2 or 3 that are released was considered the same as the impacting neutron, in which case it was not captured. But fission is treated just like n,gamma.

Thanks,

-Will
 
cooper7d7 said:
Makes sense, I was just thinking that maybe one of the 2 or 3 that are released was considered the same as the impacting neutron, in which case it was not captured..
Will,

You really can't do what you suggest of considering one of the fission neutrons as to
be the same as the impacting neutron.

Label all your neutrons with their energies. Now consider a case of "thermal fission";
that is a low energy or "thermal neutron" causes a fission; which in a thermal reactor
is the most common type of fission.

So the impacting neutron has low energy, while the 2-3 fission neutrons have high
energy. Because of the energy difference between the impacting neutron [ low energy ]
and the fission neutrons [ high energy ], you can't consider ANY of the fission
neutrons to be a "continuation" of the impacting neutron.

Dr. Gregory Greenman
Physicist
 
Hello everyone, I am currently working on a burnup calculation for a fuel assembly with repeated geometric structures using MCNP6. I have defined two materials (Material 1 and Material 2) which are actually the same material but located in different positions. However, after running the calculation with the BURN card, I am encountering an issue where all burnup information(power fraction(Initial input is 1,but output file is 0), burnup, mass, etc.) for Material 2 is zero, while Material 1...
Back
Top