When I calculate the tritium production of thermal neutrons impinge water, I found the results between MCNP and FLUKA has a difference about an order of magnitude. I assume that the deuterium in natural water would explain this gap. I adjust the atom fraction of water, but the result didn’t occur some difference.
The question is that I want to know how FLUKA deal with the multi_capture reaction like H(n,g)D,D(n,g)T.
thank you for your question. In FLUKA it is not possible to simulate a chain of multiple reaction after each other. In other words, in pure H, you would be able to simulate only H(n,g)D.
Adding deuterium to water, as you mentioned, would allow you to simulate D(n,g)T interactions.
Could you perhaps share the inputfile, the *.out file and your scorings? I can check if there anything weird in there.
Thank you for your answer. Here is my inputfiles and out file. I used the default H and O element to define water in the water_cube_1.inp while added extra D element in the water_cube_2.inp. But it seem the result is quite close. water_cube_2.lis (1.7 KB) water_cube_2.inp (4.4 KB) water_cube_1.lis (1.7 KB) water_cube_1.inp (3.2 KB)
Your files seem correct. Let me try to assess the situation with you:
If my calculations are correct, your beam contains 1.8E22 thermal neutrons.
After your irradiation time, you expect 4.32E20 H(n,γ)D reactions in your sample. I agree with that. However, there may be a typo in your table—should your yield for D(n,γ)T be 4.2E-9 [nuclide/cm³/pr]?
To investigate potential issues with the D(n,γ)T cross section, I recommend performing a simulation where, instead of natural water, you directly use heavy water (D₂O) as the medium.
Now, regardless of any differences you may observe between the two codes, let me highlight what I believe to be a more fundamental issue:
You start the simulation with 1 gram of water as the material. In this gram of water, you have 6.7E22 H and D atoms, of which only 1E19 are D atoms.
After the total irradiation time, you have produced an additional 4.32E20 D atoms. This means your material composition changes significantly during irradiation. Even with a perfect cross-section, this would lead to a severe underestimation of tritium production. The only way to address this issue is to split the calculation into several sub-simulations.
First of all, thank you for pointing out my typo in my table. It actually is 4.2E-9[nuclide/cmc/pt] while 6.91E-6 is the yield of 17O.
Then, about the D(n,γ)T corss section issue, I simulated thermal neutrons injected the pure heavy water to produce tritium before a couple days ago and found the gap of FLUKA and MCNP is small in the total amount of the tirtium where the MCNP’s reslut is 1.11E9 and FLUKA’s result is 1.03E9. It may proves the D(n,γ)T cross section correct.
As for the material compsition problem, I have derivated a simplest theoretic formula with taking into account it and neglecting the effect of neutron scattering and energy loss. The value of tritium comes to 5.782E15 . I should reconsider the effect of material compsition.
Lastly, you said that In FLUKA it is not possible to simulate a chain of multiple reaction after each other, so is it reasonal for me to assume it can’t produce tritium if I use pure H element to simulate? But the fact is that it really appears. So may be the element H will contain the 0.003% D in FLUKA.
This is indeed quite far away from your calculation in both codes.
Lastly, you said that In FLUKA it is not possible to simulate a chain of multiple reaction after each other, so is it reasonal for me to assume it can’t produce tritium if I use pure H element to simulate?
This is indeed correct. In your geometry, you selected natural Hydrogen as material (and cross section). You can find more references about the materials and cross sections: