Question about cross section reaction rates for use in XSDRNPM

[Alejandra Jolodosky]

I'm new to running SCALE and doing some quick calculations in XSDRNPM to find out the tritium production in a fusion blanket made up of a lithium ternary alloy. 

My problem has a user defined fixed source. I'm using the v7-200n47g library. To find the total tritium production, I requested MT 205 for lithium 6 and 7. However, the output indicates the activities for this MT is zero. When I use MT 105 (for Li-6) I get a result. I'm confused as to why MT 205 does not work. Do only certain MT numbers work for specific isotopes to identify cross sections?

I also tried using MT 301 to get the total kerma for other isotopes in my problem and that also does not work. 

I'm attaching my input file with only tritium production rates identified. 

Thank you for your help,

Alejandra Jolodosky