1. Effect of radial void distribution within fuel assembly on assembly neutronic characteristics;Ama;J. Nucl. Sci. Technol.,2002
2. Briesmeister, J.F., 2000. MCNP™ – A General Monte Carlo N-Particle Transport code – Version 4C. LA-13709-M, Los Alamos National Laboratory.
3. Nonuniform void effect on BWR lattice reactivity;Chiang;Trans. Am. Nucl. Soc.,1994
4. Analysis of BWR bundles with nonuniform void within the channel;Edenius;Trans. Am. Nucl. Soc.,1980
5. 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 of America.