How to simulate a D-D neutron generator with MCNP6?

AI Thread Summary
The discussion centers on simulating a neutron generator, specifically D-D reactions, using MCNP6. The original poster is seeking methods to replicate neutron angular distribution measurements, noting that MCUNED, which works with MCNPX, is not compatible with MCNP6. Suggestions include using DROSG-2000 for angular distribution data, although the poster struggles with energy probability calculations. Another participant mentions using classical energy conservation to determine neutron energy in various directions and provides a basic outline for modeling a non-isotropic source in MCNP. The conversation highlights the challenges and potential solutions for accurately simulating neutron emissions in MCNP6.
Hector_KIT
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Hello everybody,

I am performing some experiments with a neutron generator. Specifically D-D reactions. I am trying to replicate the measurements with MCNP6, but I do not know how can I simulate the neutron generator with MCNP6 since the neutrons have a angular distribution. For MCNPX there was the MCUNED code which can represent the angular dependence, but it does not work with MCNP6. Another option may be to use DROSG-2000 to obtain the angular distribution and use it as source for MCNP6, but I am not able to obtain the probability of each energy.
Does anyone know any way to do it with MCNP6, or a complementary program similar to the above described?

Best regards
HSS
 
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I'm not entirely sure about the syntax, but MCNP5 does have the option to explicitly model a source with an angular distribution of particles emitted. Is that what you're looking for?
 
Hector_KIT said:
Hello everybody,

I am performing some experiments with a neutron generator. Specifically D-D reactions. I am trying to replicate the measurements with MCNP6, but I do not know how can I simulate the neutron generator with MCNP6 since the neutrons have a angular distribution. For MCNPX there was the MCUNED code which can represent the angular dependence, but it does not work with MCNP6. Another option may be to use DROSG-2000 to obtain the angular distribution and use it as source for MCNP6, but I am not able to obtain the probability of each energy.
Does anyone know any way to do it with MCNP6, or a complementary program similar to the above described?

Best regards
HSS
Hello Hector,

I'm curious if you have found a solution to this problem since it has been posted. I am personally working on a D-T generator project at Oregon State and am about to run into the problem of distribution.

Kirk
 
Hi,
For my part I will calculate the energy of neutrons in different direction with classical energy conservation applied to the reaction (see for example chpter 4 of this book https://www.amazon.com/dp/3319486586/?tag=pfamazon01-20)
After that put a non istropic source in mcnp with dir :
SDEF DIR=d1 fdir=d2 vec= 0 0 1
SI1 H cos (teta1) cos (teta2) cos (teta3) ...
SP1 0 S1/S S2/S ...
DS2 s 10 20 30 ...
SI10 L energy_for_teta1
SI20 energy_for_teta2
SI30 energy_for_teta3
SP10 d 1
SP20 d 1
SP30 d 1

PSR
 
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