NESC0567 3DB (Abstract last modified 01-OCT-1974)
1.
NAME OR DESIGNATION OF PROGRAM - 3DB 2.
COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE -
To request or retrieve programs click on the one of the active versions below.
A password and special authorization is required. Explanation of the status codes.
Machines used:
Package-ID Orig.Computer Test Computer
NESC0567/02 IBM 370 series IBM 370 series
3.
DESCRIPTION OF PROBLEM OR FUNCTION - 3DB is a three-dimensional 4.
METHOD OF SOLUTION - Eigenvalues are computed by standard source- 5.
RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM - Since variable 6.
TYPICAL RUNNING TIME - A keff calculation with a 20 x 20 x 20 mesh 7.
UNUSUAL FEATURES OF THE PROGRAM - The input data are arranged so 8.
RELATED AND AUXILIARY PROGRAMS - The format of the input data 9.
STATUS 10.
REFERENCES - 11.
MACHINE REQUIREMENTS - 65K word memory and 11 peripheral storage 12.
PROGRAMMING LANGUAGE(S) USED - 13.
OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED - EXEC8 14.
OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS - Due 15.
NAME AND ESTABLISHMENT OF AUTHORS - 16.
MATERIAL AVAILABLE - 17.
CATEGORIES - Keywords: BURNUP, CRITICALITY, DIFFUSION EQUATIONS, FAST REACTORS, MULTIGROUP, R-THETA-Z, THREE-DIMENSIONAL, TRIANGULAR-Z, X-Y-Z
Program-name Package-ID Status
3-DB NESC0567/01 Obsolete
3-DB NESC0567/02 Tested
(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 -
(a) compute keff and perform criticality searches on time
absorption, reactor composition, and reactor dimensions by
means of either a flux or an adjoint model,
(b) compute material burnup using a flexible material shuffling
scheme, and
(c) compute flux distributions for an arbitrary extraneous
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.
dimensioning is employed, no simple bounds can be stated.
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 code can be used easily for keff and search calculations
without burdening the user with burnup parameters.
(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.
NESC0567/01: 22-APR-1988 Obsolete
NESC0567/02: 01-OCT-1974 Tested at NEADB
- K.D. Lathrop,
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).
NESC0567/02:
- R.W. Hardie and W.W. Little, Jr.:
A Three-Dimensional Diffusion Theory Burnup Code
BNWL-1264 (March 1970).
- ETIME,ETIMEF,SETDR Descriptions, excerpt from CSCXRJE/CRJE
Reference, Vol. 2, Library Elements
E00003-02-00 (April 1971).
devices (UNIVAC1108), 500K bytes and same number of mass storage
units (IBM360)
NESC0567/02: FORTRAN-IV
(UNIVAC1108), OS/360 (IBM360).
to differences in word size, the IBM version uses double
precision. In addition, certain I/O routines from the UNIVAC
library had to be written in FORTRAN for the IBM version.
1108 R. W. Hardie and W. W. Little, Jr.
Hanford Engineering Development Laboratory
Westinghouse Hanford Company
P. O. Box 1970
Richland, Washington 99352
360 W. Mroz
Applied Mathematics Division
Argonne National Laboratory
9700 South Cass Avenue
Argonne, Illinois 60439
NESC0567/02:
NESC0567_02.001 SOURCE PROGRAM (F4) 3804 records
NESC0567_02.002 SAMPLE CASE DATA 76 records
NESC0567_02.003 JCL 30 records
NESC0567_02.004 SAMPLE CASE PRINTED OUTPUT 644 records
- D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics
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