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

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Discussion Overview

The discussion revolves around simulating a deuterium-deuterium (D-D) neutron generator using MCNP6, focusing on the challenges of representing the angular distribution of emitted neutrons. Participants explore various methods and tools that could assist in achieving accurate simulations.

Discussion Character

  • Technical explanation
  • Exploratory
  • Debate/contested

Main Points Raised

  • One participant expresses uncertainty about how to simulate the angular distribution of neutrons in MCNP6, noting that MCUNED, which was available for MCNPX, is not compatible with MCNP6.
  • Another participant mentions that MCNP5 has options for modeling sources with angular distributions, questioning if this feature is what the original poster seeks.
  • A different participant proposes calculating neutron energy in various directions using classical energy conservation principles and suggests a method for implementing a non-isotropic source in MCNP.
  • There is a mention of using DROSG-2000 to obtain angular distributions, but concerns are raised about difficulties in determining the probability of each energy level.

Areas of Agreement / Disagreement

Participants do not reach a consensus on the best method for simulating the neutron generator in MCNP6, and multiple competing approaches are presented without resolution.

Contextual Notes

Some limitations include the potential incompatibility of certain tools with MCNP6 and the need for further clarification on the implementation of angular distributions and energy probabilities.

Who May Find This Useful

This discussion may be useful for researchers and practitioners involved in neutron generation simulations, particularly those using MCNP6 or similar software for modeling particle emissions.

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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