1. A fast and reliable calculation model for BWR fuel assembly burnup analyses;Jagannathan;Annals of Nuclear Energy,1980
2. An assessment of the BWR fuel box lattice cell homogenization procedures with the Tarapur BWR incore and excore measurements;Jagannathan;Annals of Nuclear Energy,1983
3. Jagannathan V., Jain R.P., in preparation a. EXCEL – A Combination of 1-D Transport and 2-D Diffusion Methods for Burnup Analysis of Hexagonal Lattice Assemblies (B.A.R.C. report).
4. Jagannathan, V., Jain, R.P., in preparation b. TRIHEX-FA – A Versatile 3-D Multigroup Diffusion Code for Steady State Core Follow up Analysis of Hexagonal Reactor Cores Using Fine Triangular Right Prismatic Meshes (B.A.R.C. report).
5. Jagannathan, V., in preparation. HEXPIN – A 3-D Multigroup Diffusion Code for Stead State Core Follow up Analysis of Hexagonal Reactor Cores Using a Pin by Pin Hexagonal Geometric Grids (B.A.R.C. report under preparation).