1. Partial Differential Equations of Mathematical Physics;Bateman,1932
2. Comparison among MCNP-based depletion codes applied to burnup calculations of pebble-bed HTR lattices;Bomboni;Nucl. Eng. Des.,2010
3. Briesmeister, J.F. (Ed.), 2000. MCNP – A General Monte Carlo N-Particle Code, Version 4C, Los Alamos National Laboratory, LA-13709-M.
4. Carpenter, David C., Wolf, Joseph H., III, 2010. The log linear rate constant power depletion method. In: PHYSOR, Pittsburgh, Pennsylvania, USA, May 9–14.
5. ORPHEE research reactor: 3D core depletion calculation using Monte-Carlo code TRIPOLI-4®;Damian;Ann. Nucl. Energy,2015