- R.D. Lawrence:
Progress in Nodal Methods for the Solution of the Neutron
Diffusion and Transport Equations
Prog. Nucl. Energy, 17, 3, 271 (1986)
- P.J. Finck and K.L. Derstine:
The Application of Nodal Equivalence Theory to Hexagonal Geometry
Proceedings of the International Topical Meeting Advances in
Mathematics, Computations and Reactor Physics, Pittsburgh, Pa.,
Vol. 4, pp 16.1 4-1 (1991)
- D. O'Dell:
Standard Interface Files and Procedures for Reactor Physics Codes
UC-32, Los Alamos Scientific Laboratory (September 1977)
- B.J. Toppel:
A Users Guide for the REBUS-3 Fuel Cycle Analysis Capability
Argonne National Laboratory, ANL-83-2 (1983)
CCC-0649/002, included references:
- K. L. Derstine:
DIF3D: A Code to Solve One-, Two-, and Three-Dimensional Finite-Difference
Diffusion Theory Problems," ANL-82-64 (1984).
- R. D. Lawrence:
The DIF3D Nodal Neutronics Option for Two- and Three-Dimensional
Diffusion Theory Calculations in Hexagonal Geometry," ANL-83-1 (1983).
- G. Palmiotti, E. E. Lewis, and C. B. Carrico:
VARIANT: VARIational Anisotropic Nodal Transport for Multidimensional
Cartesian and Hexagonal Geometry Calculation," ANL-95/40 (October 1995).
- C. H. Adams, et.al.:
The Utility Subroutine Package Used by Applied Physics
Division Export Codes," ANL-83-3 (May 1992).