Optimizing Activation Coil Selection for Maximum Gamma Flux

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    Activation Coil
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SUMMARY

The discussion focuses on optimizing activation coil selection to achieve maximum gamma flux using activation materials 27Al, 58Ni, and 115In with a PuBe neutron source at 4.5 MeV. Participants emphasize the importance of understanding the specific nuclear reactions and their corresponding cross-sections: n + 27Al → 24Na + α, n + 58Ni → 58Co + p, and n + 115In → 115Inm + n’. The analysis indicates that the choice of foil directly impacts the gamma flux detected, necessitating detailed calculations and data on reaction cross-sections and detector sensitivity.

PREREQUISITES
  • Understanding of nuclear reactions and decay processes
  • Familiarity with MCNP (Monte Carlo N-Particle Transport Code) for radiation transport simulations
  • Knowledge of neutron activation analysis techniques
  • Access to cross-section data for relevant nuclear reactions
NEXT STEPS
  • Research the cross-section data for the reactions involving 27Al, 58Ni, and 115In
  • Learn how to perform MCNP calculations for gamma flux determination
  • Investigate the half-life and decay characteristics of 115mIn
  • Study the sensitivity parameters of gamma detectors used in activation analysis
USEFUL FOR

This discussion is beneficial for nuclear physicists, radiation safety professionals, and researchers involved in neutron activation analysis and gamma spectroscopy optimization.

shakystew
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What is best way to figure out which of these activation coils would yield a higher gamma flux:

27Al, 58Ni, and 115In.

I have a PuBe neutron source, which I am told to just use a 4.5MeV neutron-energy. I am running MCNP calculations to find flux at a point away from the foil.

I knows the reactions:
n + 27Al → 24Na + α
n + 58Ni → 58Co + p
n + 115In → 115Inm + n’

Which foils will yield the highest and lowest fluxes on the detector?
 
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You'll need the cross-sections for those reactions (and the half-life of 115mIn) and some data about the sensitivity of the detector.
 

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