2-Neutron Correlation

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Big Detector Solid Angle Calculations

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


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