1. NAME AND TITLE
3DB: A Three-Dimensional Multigroup Diffusion Theory Code System for Fast Reactor
Criticality and Burnup Analysis.
2. CONTRIBUTOR
Battelle Northwest Laboratory, Richland, Washington.
3. CODING LANGUAGE AND COMPUTER
Fortran IV; CDC.
4. NATURE OF PROBLEM SOLVED
3DB is a three-dimensional (X-Y-Z, R-theta-Z, triangular-Z), multigroup diffusion code for use
in detailed fast reactor criticality and burnup analysis. The code can be used to: 1) compute keff and
perform criticality searches on buckling, time absorption, reactor composition, and reactor dimensions
by means of either a flux or an adjoint model, 2) compute material burnup using a flexible material
shuffling scheme, 3) compute flux distributions for an arbitrary extraneous source.
5. METHOD OF SOLUTION
3DB can perform criticality searches on buckling, time absorption, material concentrations, and region dimensions. Alpha and keff can be used as parametric eigenvalues. Criticality searches can be performed during burnup to compensate for fuel depletion.
Variable dimensioning is used to make maximum use of the available fast memory. Since data for
only one energy group and one plane are in the fast memory at any given time, the storage
requirements are insensitive to the number of energy groups and the number of Z intervals.
6. RESTRICTIONS OR LIMITATIONS
Since variable dimensioning is employed, no simple restrictions on problem complexity can be
stated.
7. TYPICAL RUNNING TIME
Running time (for a keff calculation) on a UNIVAC 1108 is about 1/2 hour for a 20 × 20 × 20
mesh problem using 2 energy groups. Each successive burnup time step takes about 1/4 of the above
time. No study has been made by RSIC of typical running times for 3DB on the CDC computer.
8. COMPUTER HARDWARE REQUIREMENTS
3DB is operable on the CDC computer. It requires a 65 K memory storage and eleven peripheral
storage units.
9. COMPUTER SOFTWARE REQUIREMENTS
A Fortran IV compiler is required.
10. REFERENCE
R. W. Hardie and W. W. Little, Jr., "3DB, A Three-Dimensional Diffusion Theory Burnup
Code," BNWL-1264 (March 1970).
11. CONTENTS OF CODE PACKAGE
Included are the referenced document and one (1.2MB) DOS diskette which contains the source
codes and sample problem input.
12. DATE OF ABSTRACT
January 1982.
KEYWORDS: MULTIGROUP; DIFFUSION THEORY; COMPLEX GEOMETRY; NEUTRON; BURNUP