|Program name||Package id||Status||Status date|
|Package ID||Orig. computer||Test computer|
|NESC0567/02||IBM 370 series||IBM 370 series|
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
compute keff and perform criticality searches on time absorption, reactor composition, and reactor dimensions by means of either a flux or an adjoint model,
compute material burnup using a flexible material shuffling scheme, and
compute flux distributions for an arbitrary extraneous source.
Eigenvalues are computed by standard source-iteration techniques. Group rebalancing and successive overrelaxation with line inversion are used to accelerate convergence. Adjoint solutions are obtained by inverting the input data and redefining the source terms. Material burnup is by reactor zone. The burnup rate is determined by the zone and energy-averaged cross sections which are recomputed after each time-step. The isotopic chains, which can contain any number of isotopes are formed by the user. The code does not contain built- in or internal chains.
A keff calculation with a 20 x 20 x 20 mesh using 2 energy groups requires approximately 30 minutes on a UNIVAC1108. Each successive burnup time-step takes about a quarter of the above time. On an IBM360/195 compilation and link edit require about 1 minute and execution about 7 minutes for the sample problem with 10 x 10 x 10 mesh using 2 zones and 2 energy groups.
The format of the input data (e.g. cross sections, geometry, and composition specifications) is compatible with the one- and two-dimensional transport codes DTF4 (NESC Abstract 209) and 2DF (NESC Abstract 173), the perturbation code PERT5, the one-dimensional cross section generating code 1DX (NESC Abstract 374), and the two-dimensional diffusion burnup code 2DB (NESC Abstract 325). All six codes use the same input module.
|Package ID||Status date||Status|
|NESC0567/02||01-OCT-1974||Tested at NEADB|
DTF-IV, A FORTRAN-IV Program for Solving the Multigroup Transport Equation with Anisotropic Scattering LA-3373 (July 15, 1965).
2DF, A Two-dimensional Transport Code Developed at the Los Alamos Scientific Laboratory, (unpublished). - R.W. Hardie and W.W. Little, Jr., PERT-V, A Two-dimensional Perturbation Code for Fast Reactor
Analysis, BNWL-1162 (September 1969).
R.W. Hardie and W.W. Little, Jr.,
1DX, A One-dimensional Diffusion Code for Generating Effective Nuclear Cross Sections, BNWL-954 (March 1969).
W.W. Little, Jr. and R.W. Hardie,
2DB User's Manual Revision 1 BNWL-831, Rev. 1 (February 1969).
|Package ID||Computer language|
1108 R. W. Hardie and W. W. Little, Jr.
Hanford Engineering Development Laboratory
Westinghouse Hanford Company
P. O. Box 1970
Richland, Washington 99352, USA
360 W. Mroz
Applied Mathematics Division
Argonne National Laboratory
9700 South Cass Avenue
Argonne, Illinois 60439, USA
|File name||File description||Records|
|NESC0567_02.001||SOURCE PROGRAM (F4)||3804|
|NESC0567_02.002||SAMPLE CASE DATA||76|
|NESC0567_02.004||SAMPLE CASE PRINTED OUTPUT||644|
Keywords: burnup, criticality, diffusion equations, fast reactors, multigroup, r-theta-z, three-dimensional, triangular-z, x-y-z.