Difference between revisions of "CrossTalk"
| Line 21: | Line 21: | ||
The number of n-n coincidences was a factor of 30 times greater than the number of n-crosstalk coincidences. I have defined an n-n coincidence event as two or more neutrons from the same fission registering a hit in two different detectors. An n-crosstalk coincidence event is defined as a singe source neutron (or any secondaries it produces) registering a hit in two different detectors. | The number of n-n coincidences was a factor of 30 times greater than the number of n-crosstalk coincidences. I have defined an n-n coincidence event as two or more neutrons from the same fission registering a hit in two different detectors. An n-crosstalk coincidence event is defined as a singe source neutron (or any secondaries it produces) registering a hit in two different detectors. | ||
| − | [[File: | + | [[File:CrosstalkVScoincidence.png|750px]] |
Go back [[MCNP simulations]] | Go back [[MCNP simulations]] | ||
Revision as of 21:40, 17 February 2017
Go back MCNP simulations
Old simulations
Simulation geometry
An array of 6 detectors are placed radially at a distance of 1 meter from a correlated CF-252 source. The image below shows a top down view of the simulation geometry. The detector setups have a vertical extent of 30".
Simulation detector physics
The detector physics used in the simulation are MCNP-POLIMI's default treatment for plastic organic scintillators. POLIMI uses electron equivalent light output (MeVee) for simulating detector response. I assumed the detectors have a neutron energy deposition threshold of 0.2 MeV, giving an equivalent light output threshold of 0.03 MeVee.
Neutron energy deposition from collisions with both hydrogen and carbon are converted to electron equivalent light output (MeVee). All neutron collisions that occur within a pulse collection time window of 10 ns of each other are converted to MeVee and summed. If the cumulative light output of a pulse exceeds the 0.03 MeVee threshold, then a detection is registered. The value 0.03 MeVee was chosen because it corresponds to a mean neutron energy deposit of 0.2 MeV. The detectors in the simulation had a 55% efficiency for detecting CF-252 neutrons.
Simulation source
POLIMI is used to simulate a correlated CF-252 SF source. The source neutrons are correlated by angle, energy, and multiplicity. The mean multiplicity of the source is 2.7 neutrons/fission. A correlated n-n opening angle distribution (shown below) is produced by dividing the opening angle distribution of neutrons selected from single fissions, by the opening angle distribution of neutrons selected from separate fissions.
Simulation results
The number of n-n coincidences was a factor of 30 times greater than the number of n-crosstalk coincidences. I have defined an n-n coincidence event as two or more neutrons from the same fission registering a hit in two different detectors. An n-crosstalk coincidence event is defined as a singe source neutron (or any secondaries it produces) registering a hit in two different detectors.
Go back MCNP simulations