1. MCNP—A general Monte Carlo Code for Neutron and Photon Transport, LA-13709-M,2000
2. M. Herman, A.B. Pashchenko, Extension and improvement of the FENDL library for fusion applications (FENDL-2), Report INDC (NDS)-373, IAEA, Vienna, 1997.
3. ATTILA: comprehensive radiation transport solution environment, http://www.radiative.com/Attila-010505.pdf.
4. Comparing the prediction of “Attila” code to the experimental data of fusion integral experiments and to the results of MCNP code;Youssef,2006
5. Benchmarking the CAD-based ATTILA discrete ordinates code with experimental data of fusion experiments and to the results of MCNP code in simulating ITER;Youssef,2007