1. Nuclear Reactor Theory;Bell,1970
2. The aircraft reactor experiment – design and construction;Bettis;Nucl. Sci. Eng.,1957
3. Bowman, S.M., Dunn, M.E., Hollenbach, D.F., Jordan, W.C., 2005. Scale Cross Section Libraries. Technical Report, ORNL/TM-2005/39.
4. Briesmeister, J.F., 2000. MCNP – A General Monte Carlo N-Particle Transport Code. Technical Report, LA-13709-M, Los Alamos National Laboratory.
5. Cammi, A., Di Marcello, V., Fiorina, C., Luzzi, L., 2009. Assessment of COMSOL capabilities to analyse the thermo-hydrodynamic behaviour of the MSR core. In: Proceedings of the COMSOL Conference 2009, Milan, Italy, CD-ROM, COMSOL, Inc.