Difference between revisions of "2NCorr Photon flux estimate"

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;<math> n_{rate} = N_{\gamma}\Omega\epsilon \int_{2.3}^{10.5}\! (1.89 e^{-0.54E})*(0.21\sigma(E))\,dE</math>
 
;<math> n_{rate} = N_{\gamma}\Omega\epsilon \int_{2.3}^{10.5}\! (1.89 e^{-0.54E})*(0.21\sigma(E))\,dE</math>
  
The unknown detector efficiency can be set to 1, which brings <math>N_{\gamma}</math> to its theoretical minimum, which is roughly 1,000 photons per pulse. The detector efficiency is not known exactly, but it lies in the range of 5-25%.  
+
The unknown detector efficiency can be set to 1, which brings <math>N_{\gamma}</math> to its theoretical minimum, which is roughly 1,000 photons per pulse. The detector efficiency is not known exactly, but it lies in the range of 5-25%, so there are between 4,000 and 20,000 photons above 2.3MeV incident on the target. Each photon can be considered a independent "binomial trial", and with such a large number of trials, Poissian distribution is a good approximation for the distribution of the number of photo-nuclear reactions per pulse.  
  
 
[[File:2NCorrPhotonFluxRate.png|thumb| 500px| left|Photon flux on the target over a range of photon energies, estimated from observed neutron rates, while assuming the detector array's intrinsic efficiency is 100%. Correcting for an efficiency less than 100% is done by dividing the distribution by the efficiency.]]
 
[[File:2NCorrPhotonFluxRate.png|thumb| 500px| left|Photon flux on the target over a range of photon energies, estimated from observed neutron rates, while assuming the detector array's intrinsic efficiency is 100%. Correcting for an efficiency less than 100% is done by dividing the distribution by the efficiency.]]

Revision as of 06:25, 4 January 2018

Overview

An estimated lower bound for the photon flux throughout the experiment can be calculated from the data of a D2O target. The measured neutron rate from D2O depends on the following: the (G,n) cross-section as a function of energy, the energy distribution of the brem photons, target geometry, detector efficiency, and photon flux. The (G,n) cross-sections are known and the brem energy distribution can be taken from an MCNP simulation. The only remaining unknown variables are photon flux and detector efficiency. By setting detector efficiency to 100%, and considering only geometric effects (i.e. solid angle), a lower bound can be placed on the photon flux incident on all targets.

Plots

  • Energy distribution of collimated bremsstrahlung photons from the passage of 10.5 MeV electrons through 1" of Al. Data is taken from an MCNP simulation.
  • 1-H-2(G,n).png

Calculation

The measured neutron rate is given by:

[math]n_{rate}= N_{\gamma}\Omega\epsilon\int_{2.3}^{10.5}\!P(E|E\gt 2.3)*P(n_0|E)* \,dE[/math]
[math]N_{\gamma}[/math] is the number of photons incident on the target with energy greater than 2.3 MeV, the threshold for photo-disintegration of D2O.
[math]E[/math] is photon energy as a function
[math]\epsilon[/math] is the detector efficiency for D2O photo-neutrons.
[math]P(n_0|E) [/math] is the probability of a photo-disintegration event given that the photon has energy E.
[math]P(E|E\gt 2.3) [/math] is the probability of a photon having energy E, given that the photon is above threshold.
[math]n_{rate}[/math] is the mean number of neutrons observed per pulse.
[math]\Omega[/math] is the solid angle for the entire detector array (0.056/4pi).

Now writing [math]P(n_0|E)[/math] in terms of the cross-section and substituting a normalized photon energy distribution taken from MCNP in place of [math]P(E|E\gt 2.3)[/math], the above becomes:

[math] n_{rate} = N_{\gamma}\Omega\epsilon \int_{2.3}^{10.5}\! (1.89 e^{-0.54E})*(0.21\sigma(E))\,dE[/math]

The unknown detector efficiency can be set to 1, which brings [math]N_{\gamma}[/math] to its theoretical minimum, which is roughly 1,000 photons per pulse. The detector efficiency is not known exactly, but it lies in the range of 5-25%, so there are between 4,000 and 20,000 photons above 2.3MeV incident on the target. Each photon can be considered a independent "binomial trial", and with such a large number of trials, Poissian distribution is a good approximation for the distribution of the number of photo-nuclear reactions per pulse.

Photon flux on the target over a range of photon energies, estimated from observed neutron rates, while assuming the detector array's intrinsic efficiency is 100%. Correcting for an efficiency less than 100% is done by dividing the distribution by the efficiency.