1. Briesmeister, J.F., 2000. MCNP – A General Monte Carlo N-Particle Transport Code, LA-13709-M Version-4C. Los Alamos National Laboratory.
2. Conceptual design of a high temperature power reactor cooled and moderated by supercritical light water;Dobayashi;Ann. Nucl. Energy,1998
3. Edenius, M., Ekberg, K., Forssen, B.H., Knott, D., 1995. CASMO-4: A Fuel Assembly Burnup Program User’s Manual, Studsvik/SOA-95/1, Studsvik.
4. Methods/data testing for advanced LWR fuel designs and operational modes in the PROTEUS facility;Jatuff;J. Nucl. Sci. Technol.,2002
5. Khalil, H., 2004. In: Minutes of the International Workshop on Reactor Physics Advances for Design and Analysis of Generation IV Nuclear Energy Systems, Chicago, IL, 30 April 2004.