1. Bahadir, T., Lindahl, S.-Ö., 2009. Studsvik’s next generation nodal code SIMULATE-5. In: Proceedings of the ANFM-2009 Conference, Advances in Nuclear Fuel Management IV (Hilton Head Island, South Carolina, USA, 2009).
2. MCNPTM-A General Monte Carlo N-particle Transport Code, Version 4C, LA-13709-M, vol. 2;Briesmeister,2000
3. SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation;Bucholz,1982
4. Theory and applications of the fission matrix method for continuous-energy Monte Carlo;Carney;Ann. Nucl. Energy,2014
5. ENDF/b-VII.1 nuclear data for science and technology: Cross sections, covariances, fission product yields and decay data;Chadwick;Nucl. Data Sheets,2011