1. Briesmeister, J.F. (Ed.), 1997. MCNP- A General Monte Carlo N-Particle Transport Code Version 4B. LA-12625-M, Los Alamos National Laboratory.
2. Liu, Y.S. et al., 1986. ANC: A Westinghouse Advanced Nodal Computer Code. WCAP-10966-A.
3. Nguyen, T.Q. et al., 1988. Qualification of the PHOENIX-P/ANC Nuclear Design System for Pressurized Water Reactor Core. WCAP-11597-A.
4. Palmer, I.D. et al., 1999. Development and Validation of the ENIGMA Code for MOX Fuel Performance Modeling. IAEA-SM-358/20.
5. Smith, L.D. et al., 1999. Modified WRB-2 Correlation, WRB-2M, for Predicting Critical Heat Flux in 17×17 Rod Bundles with Modified LPD Mixing Vane Grids. WCAP-15026-NP-A.