Question about counting rate in a detector

Click For Summary
SUMMARY

This discussion focuses on simulating a Cesium-137 source with an energy of 0.662 MeV and an activity of 225 mCi using MCNP. The user inquires whether the tally time defined by the "T: tally time bins" card can be utilized to estimate the time required for a detector to count a specific number of particles. It is concluded that while the T card measures time between particle emission and event tallying, it does not directly correlate to counting time. Instead, using the tally result (F4 multiplied by activity) is recommended to calculate the flux rate (Bq/cm².s) for determining counting time.

PREREQUISITES
  • Understanding of MCNP simulation software
  • Knowledge of particle physics, specifically regarding Cesium-137
  • Familiarity with tally cards in MCNP, particularly F4 and F8
  • Basic principles of flux measurement and activity calculations
NEXT STEPS
  • Research how to implement F8 tally in MCNP for different detector types
  • Learn about calculating flux response for various energy levels in MCNP
  • Explore the use of energy bins in MCNP for scintillator simulations
  • Investigate the implications of using the BURN card for activity over time in MCNP
USEFUL FOR

Researchers and engineers in nuclear physics, radiation detection specialists, and anyone involved in simulating particle interactions and detector responses using MCNP software.

Alexander Camargo
Messages
37
Reaction score
10
Hello everyone. I am simulating a Cesium-137 source with an energy of 0.662 MeV and an activity of 225 mCi. When I use the "T: tally time bins" card, for example:

F24:P 1
E24 20
T24 0 1000 25I 3600 196I 200600

I understand that I am asking the program to give me the average flux in this cell, for an energy of 20 MeV, over the defined time intervals (Tremor). My question is: can this time be used to determine how long it will take for my detector to count a certain number of particles? Or is this time on the T card only used for the simulation time?

Would it make more sense to use the tally result (F4 * activity) to obtain the flux rate (Bq/cm².s) to determine the time?
 
Engineering news on Phys.org
MCNP doesn't really understand macroscopic time in a simulation. It keeps track of flight time, and the BURN card understands MW.days but I don't think there is any way of telling it the activity of a source. Most tally results are per source particle, so multiplying by the source activity afterwards is the normal process (and you can multiply by arbitrary values so you can force the program to do the maths for you if you want). T card is in shakes, so it's counting time between the emission of the particle and the event being tallied. This is really useful if the simulation is of a time of flight spectrometer, for example.

E24 20, btw, would be a single bin including everything from 0 to 20 MeV.

F4 can work but then you need to determine flux response for different energies if you want to know what a detector would do. I'm assuming that is the goal because it's in the title of the thread. If your detector is a scintillator, or a germanium crystal, I would put that in the simulation and use an F8 tally. I don't know if F8s are per volume or not by default so I would be sure to check that. If this is a scintillator without an MCA you can still use energy bins to simulate the threshold setting.
 
  • Like
Likes   Reactions: Salman Khan, Alexander Camargo and Astronuc

Similar threads

  • · Replies 3 ·
Replies
3
Views
3K
  • · Replies 4 ·
Replies
4
Views
3K
  • · Replies 3 ·
Replies
3
Views
2K
  • · Replies 10 ·
Replies
10
Views
3K
  • · Replies 2 ·
Replies
2
Views
2K
  • · Replies 1 ·
Replies
1
Views
5K
  • · Replies 1 ·
Replies
1
Views
4K
Replies
4
Views
2K
  • · Replies 5 ·
Replies
5
Views
3K
  • · Replies 1 ·
Replies
1
Views
2K