Recent content by J_P_C

It finally works, although I have no idea why o0). I ran the very same input file from my previous message and this time it worked. And yes, I am in Windows. Thanks so much for the help! My original intention was to compare the flux in an innmermost pincell versus flux in an outermost pincell...

Thanks for the answer, I see what you mean. In fact, now that I know I need the sdn card I went looking into the manual and I saw that this card is especially recommended for tallies in repeated structures. I liked the idea of using the divisor just as 1 and dividing by the real value later, so...

Thanks!

Hi all, I'm new to the forum. Maybe you guys can give me hand with this. I am using MCNP4 to model a 17x17 fuel element. I want to know the average neutron flux in a specific pincell but so far everything I try results in error. This is my input (text file is attached too): c CELL CARDS 1 1...

Hello everyone. I am a Physics graduate currently finishing my Master's in nuclear science and technology. I found the forum while looking for help for a problem and I think I will stay here with you guys.