Hello @thanapong,
Let us first take a look to the mgdraw.f case:
- The USRYIELD has no relation with the mgdraw.f user routine so you can delete this card. The BXDRAW entry of that routine will be called every time a particle crosses a boundary provided that you have correctly included the USERDUMP card as we mentioned in our previous discussion, independently of whether you have a USRYIELD card or not.
- In the .txt file that you provided I can see that all neutrons are on the boundary between “tarclad” and “bord”, which is what you have requested in the mgdraw routine as far as I can tell. If you want your neutrons to be scored in the boundary between “bord” and “void” then you need to change accordingly the routine, as I believe you have done already.
- About the kinetic energy: since the total energy is provided and it is the sum of kinetic and rest energies, probably the most straightforward thing to do is to calculate it by yourself in the mgdraw routine before you print it out.
On the fluscw routine. The .txt file is not generated for two reasons:
- In the USERWEIG card you did not specify a correct value for WHAT(3) if you want fluscw to be called, see USERWEIG | FLUKA. Most likely you want to specify the value 3.
- You are using a USRYIELD scoring, but in the fluscw routine you filter out every call that is not triggered by a boundary crossing estimator (ISCRNG = 1), including those triggered by a yield estimator (ISCRNG = 5) and therefore nothing is ever written. See comments on the routine. You will need to substitute
IF (ISCRNG.EQ.1) THENbyIF (ISCRNG.EQ.5) THEN.
Hope this helps!
Francisco