2-Neutron Correlation

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Big Detector Solid Angle Calculations

Neutron Corr Home Page

MCNPX Simulation
  • 14 MeV neutron source, emitted isotropically ([math]4\pi[/math])
  • Detector placed 1m away from source

Mcnpxsetup.png

  • face of the detector is 15.24cm x 76.2cm, and 3.6cm deep

DetectorDimensions.png

The solid angle can be found from the number of particles hitting the detector as:
[math]\Delta \Omega = 4\pi*\frac{hits}{hits + misses}[/math]

Results
  • Out of 1E9 neutrons generated, 8618287 neutrons hit the detector
    • [math]\Delta \Omega = 0.108 Sr[/math]
      • if the detector is placed 70cm away from the source, [math]\Delta \Omega = 0.207 Sr[/math]
      • if the detector is placed 65cm away from the source, [math]\Delta \Omega = 0.236 Sr[/math]
  • As a test to verify our results
    • We change the detector size to 2cm by 2cm and used 1E9 neutrons again
    • 32061 neutrons struck the detector
    • [math]\Delta \Omega = 0.0004 Sr[/math]
  • And, as a second test to verify our results
    • We change the detector size to 1cm by 1cm and used 1E9 neutrons again
    • 7965 neutrons struck the detector
    • [math]\Delta \Omega = 0.0001 Sr[/math]
Now, what neutron singles rate into the detector should correspond to 1 fission per pulse?
  • If we have 1 fission per pulse and each fission emits on average 2.3 neutrons, we should expect 2.3 neutrons/pulse
  • The number of neutrons hitting the detector per pulse is found as [math]2.3*\frac{\Delta \Omega}{4\pi}[/math]
    • @ 1 meter => 0.0198 neutrons hitting the detector per pulse
    • @ 70 cm => 0.0379 neutrons hitting the detector per pulse
  • Taking into account the efficiency of the detector [math]\epsilon_0[/math], the number detected per pulse can be found as [math]2.3*\frac{\Delta \Omega}{4\pi}*\epsilon_0[/math]
    • @ 1 meter from source => ([math]0.0198*\epsilon_0=0.0198*0.17=0.003[/math]) neutrons detected per pulse
    • @ 70 cm from source => ([math]0.0379*\epsilon_0=0.0379*0.17=0.006[/math]) neutrons detected per pulse

Neutron and Photon Flux Through Lead

Using MCNPX, a simulation was done to determine how much of the neutrons and photons from the target will be blocked by various thickness of lead. With a monochromatic pencil beam of incident particles, the following results illustrate how much of the initial beam actually made it through the lead.

1MeV Lead.jpg

5MeV Lead.jpg

Neutron and Photon Flux Through Concrete

1MeV Concrete.jpg

Detector Cross-Talk

Using MCNPX, I am trying to simulated the cross-talk we could expect between the big detectors. I used a fission neutron energy spectrum given in MCNPX, shown below.

FissionNeutronEnergySpectrum.jpg

These neutrons are incident upon a plastic scintillator and I will look at the neutrons and photons coming out of the scintillator's sides perpendicular to the incident beam. The first case I will look at is where the detectors are placed with only polyethylene between them, as illustrated below.

OLead.png

This results in a neutron and photon energy spectrum as follows.

NeutronEnergySpectrum.jpg

PhotonEnergySpectrum.jpg

The next case I will look at is where we put a layer of lead between the polyethylene between the detectors, as shown in the schematic below.

DetectorSetupwLead.png

The results for this setup using 1 inch of lead between the detectors is as follows.

NeutronEnergySpectrumPb.jpg

PhotonEnergySpectrum1inPb.jpg

And, the results for this setup using 2 inches of lead between the detectors is as follows.

NeutronEnergySpectrum2Pb.jpg

PhotonEnergySpectrum2Pb.jpg

Neutron Detector TDC Spectra Thick Uranium Target

8/17

TDC8 17.png

Phi8 17.png

Theta8 17.png

8/20

TDC8 20.png

Phi8 20.png

Theta8 20.png

8/21

TDC8 21.png

4143

TDC8 21 4143.png

4144

TDC8 21 4144.png

4145

TDC8 21 4145.png

4146

TDC8 21 4146.png

8/22

TDC8 22.png

Phi8 22.png

Theta8 22.png

8/23

TDC8 23.png

Phi8 23.png

Theta8 23.png

8/24

TDC8 24.png

Phi8 24.png

Theta8 24.png

8/17 - 8/20

TDC8 17 20.png

8/17 - 8/21

TDC8 17 21.png

8/17 - 8/22

TDC8 17 22.png



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