Flux in Moderator vs Flux in fuel

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SUMMARY

The discussion focuses on the differences between neutron flux shapes in moderators and fuels within thermal reactors. The fission neutron spectrum is represented by the equation y=e^-x*sinh(sqrt(x)), while the slowing down of neutrons is proportional to 1/E. The thermal neutron spectrum is described by (E*exp(-E/kt))/T^(3/2). It is established that the neutron flux in the fuel encompasses the full spectrum, whereas the moderator flux lacks significant portions of the fission spectrum, with the fast flux being approximately three times the thermal flux in thermal reactors.

PREREQUISITES
  • Understanding of neutron flux and its mathematical representation
  • Familiarity with thermal reactor physics
  • Knowledge of fission processes and neutron interactions
  • Basic grasp of neutron spectrum analysis
NEXT STEPS
  • Research the mathematical modeling of neutron flux using Wolfram Alpha
  • Study the differences in neutron flux profiles between moderators and fuels in thermal reactors
  • Explore the impact of self-shielding on thermal neutron flux in fuel
  • Investigate the neutron spectrum in Light Water Reactors (LWRs) through academic papers
USEFUL FOR

Physicists, nuclear engineers, and students studying reactor physics or neutron transport phenomena will benefit from this discussion.

sandon
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I was reading about different flux shapes, and it depicted the the shape of the fission neutron spectrum to be in the shape of y=e^-x*sinh(sqrt(x)), where y is the spectrum and x is the energy in MeV.

note: put that equation into wolfram for easy visualization

Then it depicted the slowing down of neutrons neutron flux to be proportional to 1/E

Finally it gave the neutron spectrum of thermal neutron to be proportional to
(E*exp(-E/kt))/T^(3/2)

See attached image for full neutron spectrum

My question is how does the shape of the neutron flux in the moderator differ from the shape of the neutron flux in the fuel.

My first thoughts were neutron flux in the fuel is the full spectrum of the attached image, and the flux in the moderator does not contain as much of the fission spectrum. I can't see any other differences, but the question wants a clear indication of difference between the fuel spectrum and moderator spectrum, both dependent on energy.
 

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The fast flux is typically about 3x thermal flux in a thermal reactor.

The fission neutrons are produced with a spectrum. About 8 to 10% of fissions in a thermal reactor occur due to fast fissions of U-238.

The thermal flux in the fuel falls off radially into the fuel due to self-shielding, i.e., the fissions and reasonance absorptions diminish the neutron flux penetrates the fuel.

I will try to find a reference on the neutron spectum in an LWR.

Ref: http://meetingsandconferences.com/physor2012/Workshops/9.SFR-physics.pdf (third page)
 
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