Mcnp6 Definition and 56 Threads

Hi, I'm simulating in MCNP6 the reaction of proton beam on targets but in the simulation the 96% of the proton are lost for energy cutoff. I don't understand why happen that. I use a tally4 to obtain the reaction in the target, but I suppose the results are wrong because the lost of protons (if...

Hey all, I was wondering if anyone had any good tips on debugging mcnp geometry? I'm an intermediate user working on better understanding the program. Does anyone have any tips or tricks that go beyond simply reading the manual?

Hello everyone here, I do need your help in this matter, please kindly help me solve this problem. I am new to this forum and now am seeking for help. I am new to MCNP code, and I run MCNP6 code using BURN card and it give me fatal error say "Model required. Cannot use memory reduction...

I was running the MCNP input file. after simulation it shows that 10 particle are lost,( using MCNP6) I do not know where is a problem. How can i get to the solution?

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...

Hello Every body, I hope all is well. I have a problem with MCNP6 code for using burn card, so please can anybody help me ? --------------------------------------------------------------------------- particle maximum smallest largest always...