Recent content by Ericdjs

Sorry, the problem was fixed by myself.

My MCNPX is not working when I start the calculation. It says "bad trouble in imcn in routine xin cross-section file bertin does not exist."

Thank you ! thank you !

Thank you ! 100 Bq of Co-60 source multiply F8 by 200 because the Co-60 source has two different energies ? what if i need to calculate both low energy and high energy counts, is it correct that multiply the areas of different peaks by 200 with different percentages of both low energy particles...

I want to calculate that how many particles will be recorded by detector with MCNP. using the F8 tally which would provide energy spectrum, add all of data that related with full energy peak of spectrum, multiply by number of nps, then obtain the number of particles. is it correct ? i am not...

Hello ! I am ericdjs, it is a pleasure to join this forums.