Dear Dr. Amrani, I might offer passive help. I can provide a Fortran Alice2014 code+associated data files. If you can compile and run under linux or a windows/linux

system, it will allow an input of e.g. a fast neutron spectrum of energies in discrete 

incident energies. It will out put product yields and emitted particle spectra. You would have to make a secondary program to input the fast reactor n spectra, then take the

weighted output yields, plus transport the emitted particle spectra. This is a poorly articulated response. I may have a description of the alice nuclear reacions code

to help clarify- and yes, you would have to run as targets all the primary or long lived

fission products. Bur it would allow you to see if reactor wastes could be transmuted to

sae stable products.  Let me know if you wish a FORTRAN listing- good luck!

,marshall blann

Dear Dr. Naïma Amrani 

let us start some new thing with GEANT 4, let me know your opinion with some text material.