1. Fuel element burn-up calculation in ITU TRIGA Mark-II Reactor;Büke,2002
2. ENDF/B-VII.1: nuclear data for science and technology: cross sections, covariances, fission product yields and decay data;Chadwick;Nucl. Data Sheets,2011
3. Validation of the MONTEBURNS code for criticality calculations of TRIGA reactors;Dalle;Res. Dev. Braz. J.,2002
4. Monte Carlo simulation of TRIGA IPR-R1: reactivity worth, burnup, flux and power;Dalle,2006
5. Application of a genetic algorithm to the fuel reload optimization for a research reactor;Do;Appl. Math. Comput.,2007