I don`t think that software from Argonne National Laboratory is free, but you can always ask them:

http://www.ne.anl.gov/capabilities/rpfca/codes/

Also you can try software "serpent" :

http://montecarlo.vtt.fi/

Best regards,

Jan

Thank you @jan  but both of them are not free 

sorry Muhammad :(

DRAGON5 code is free. See www.polymtl.ca/merlin.

@Alain Hebert  thank you alain i have found it and i will start 

I think that REBUS code can do this. also the following document which describes the numerical method for nuclear fuel burnup calculation can help you.

http://passthrough.fw-notify.net/download/460821/http://lib.tkk.fi/Diss/2013/isbn9789513880002/isbn9789513880002.pdf

@Yassine Boulaich  you may missed that i need a free software and this one is not. thanks for your help 

You can use DRAGON code. Furthermore, you need microscopic cross-section libraries such as MATXS, WIMS, and APOLLO.

Thank You all For Your valuable Answers 

Dear Muhammad S. Mansy,

milonga is free and open software (GNU GPL version 3) and it solves what you need.

You can download the instructions to download it from:

https://bitbucket.org/seamplex/milonga

Or you can ask questions in the mailing list:

https://www.seamplex.com/lists.html

perhaps openMc can work if you are going to consider MC method,

hi, mcnp as a monte carlo code can help you with burn card for burnup calculations

DGRAGON , OPENMC