NESC0374 1-DX. (Abstract last modified 01-JUL-1973)
1.
NAME OR DESIGNATION OF PROGRAM - 1DX 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
NESC0374/03 IBM 370 series IBM 370 series
NESC0374/04 UNIVAC 1106 UNIVAC 1106
3.
DESCRIPTION OF PROBLEM OR FUNCTION - 1DX is a multipurpose, one- 4.
METHOD OF SOLUTION - Resonance shielded cross sections are 5.
RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM - 1DX uses variable 6.
TYPICAL RUNNING TIME - A representative 26-group problem with 30 7.
UNUSUAL FEATURES OF THE PROGRAM - 8.
RELATED AND AUXILIARY PROGRAMS - The format of the input data 9.
STATUS 10.
REFERENCES - 11.
MACHINE REQUIREMENTS - 65K memory and 7 peripheral storage devices 12.
PROGRAMMING LANGUAGE(S) USED - 13.
OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED - OS/360,370 14.
OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS - 15.
NAME AND ESTABLISHMENT OF AUTHORS - 16.
MATERIAL AVAILABLE - 17.
CATEGORIES - Keywords: CRITICALITY SEARCHES, CROSS SECTIONS, DIFFUSION, FAST REACTORS, ITERATIVE METHODS, ONE-DIMENSIONAL
Program-name Package-ID Status
1-DX NESC0374/01 Obsolete
1-DX NESC0374/02 Obsolete
1-DX NESC0374/03 Tested
1-DX NESC0374/04 Tested
dimensional diffusion code for generating cross sections to be
used in fast reactor analyses. The code is designed to -
(a) compute and punch resonance shielded cross sections using
data in the Russian (see reference 2) format,
(b) compute and punch group-collapsed microscopic and/or
macroscopic cross sections averaged over the spectrum in
any specified zone, and
(c) compute keff and perform criticality searches on time
absorption, material concentrations, zone dimensions, and
buckling using either a flux or an adjoint model.
calculated using data (infinite dilution cross sections and
resonance shielding factors) in the Russian format. Interpolation
schemes are used to compute shielding factors applicable to
specific compositions. A flux iteration option for computing the
elastic removal cross section is also included. Group-collapsed
cross sections by reactor zone are calculated using flux
weighting. The eigenvalue and spatial flux profiles are computed
using standard source-iteration techniques. Convergence is
accelerated using fission source overrelaxation. 1DX will also
accept input cross sections in the DTF format (i.e., resonance
shielded cross sections).
dimensioning to make maximum use of existing core storage. All
subscripted variables are stored in one array dimensioned to
35,000 on the UNIVAC1108. Allocation is dynamic in the IBM
version.
spatial intervals using data in the Russian format requires about
50 seconds on a UNIVAC1108. If the cross section data is already
in the DTF format, the same problem would require about 5 seconds.
The sample problem requires 12 seconds of CPU time on an
IBM370/195.
(e.g., flux dumps, geometry and composition specifications, etc.)
is compatible with Los Alamos one- and two-dimensional transport
codes DTF4 (NESC Abstract 209) and 2DF (NESC Abstract 173), the
BNW two-dimensional burnup code 2DB (NESC Abstract 325), and the
BNW perturbation code PERT4 (NESC Abstract 304). The computer
code ETOX will prepare cross section data in the Russian format
from the ENDF/B data tape. PUPX is an auxiliary program that
prints, updates, and punches cross section data in the Russian
format using a binary tape.
NESC0374/01: 20-APR-1988 Obsolete
NESC0374/02: 21-APR-1988 Obsolete
NESC0374/03: 01-DEC-1972 Tested at NEADB
NESC0374/04: 01-JUL-1973 Tested at NEADB
- I.I. Bondarenko, et al.,
Group Constants for Nuclear Reactor Calculations, Consultants
Bureau, New York, 1964.
- 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 from the Los Alamos
Scientific Laboratory (unpublished).
- R.W. Hardie and W.W. Little, Jr.,
PERT-IV, A Two-dimensional Perturbation Code in FORTRAN-IV
BNWL-409, April 1967.
- R.E. Schenter, J.L. Baker, and R.B. Kidman,
ETOX, A Code to Calculate Group Constants for Nuclear Reactor
Calculations
BNWL-1002, May 1969.
NESC0374/03:
- R.W. Hardie and W.W. Little, Jr.:
1-DX, 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).
NESC0374/04:
- R.W. Hardie and W.W. Little, Jr.:
1-DX, 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).
(UNIVAC1108), 145K and maximum of 8 storage devices (IBM360,370)
NESC0374/03: FORTRAN-IV
NESC0374/04: FORTRAN-IV
(IBM360,370).
1108 R. W. Hardie
Pacific Northwest Laboratories
Battelle
P. O. Box 999
Richland, Washington 99352
360,370 H. Henryson, II
Applied Physics Division
Argonne National Laboratory
9700 South Cass Avenue
Argonne, Illinois 60439
NESC0374/03:
NESC0374_03.001 1-DX SOURCE PROGRAMME 3018 records
NESC0374_03.002 DD,OVERLAY CARDS+SAMPLE INPUT 452 records
NESC0374_03.003 AUXILIARY ROUTINE PUPX SOURCE 216 records
NESC0374_03.004 SAMPLE OUTPUT OF 1-DX 1177 records
NESC0374/04:
NESC0374_04.001 SOURCE PROGRAM (FORTRAN) + SAMPLE INPUT 1208 records
NESC0374_04.002 SAMPLE OUTPUT 1110 records
- B. Spectrum Calculations, Generation of Group Constants and Cell Problems
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