|Program name||Package id||Status||Status date|
|Package ID||Orig. computer||Test computer|
|NESC0325/02||IBM 360 series||IBM 360 series|
2DB is a flexible, two-dimensional (x-y, r-z, r-theta, hex geometry) diffusion code for use in fast reactor analyses. The code can be used to:
Compute fuel burnup using a flexible material shuffling scheme.
Perform criticality searches on time absorption (alpha), material concentrations, and region dimensions using a regular or adjoint model. Criticality searches can be performed during burnup to compensate for fuel depletion.
Compute flux distributions for an arbitrary extraneous source.
Standard source-iteration techniques are used. Group rebalancing and successive overrelaxation with line inversion are used to accelerate convergence. Material burnup is by reactor zone. The burnup rate is determined by the zone and energy (group) 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.
Since variable dimensioning is employed, no simple bounds can be stated. The current 1108 version, however, is nominally restricted to 50 energy groups in a 65K memory. In the 6600 version the power fraction, average burnup rate, and breeding ratio calculations are limited to reactors with a maximum of 50 zones.
The input data (e.g., cross sections, flux dumps, geometry, and composition specifications) are compatible with the Los Alamos one- and two-dimensional transport codes, DTF4 (NESC Abstract 209) and 2DF, and the Battelle perturbation code, PERT4 (NESC Abstract 304). All four codes use the same input module. The logical flow of 2DB is patterned after the 2DF code.
|Package ID||Status date||Status|
|NESC0325/02||01-JAN-1969||Tested at NEADB|
W.W. Little, Jr. and R.W. Hardie,
2DB, A Two-dimensional Diffusion-Burnup Code for Fast Reactor Analysis, BNWL-640, January 1968, Addendum and Errata, April 12, 1968.
T.J. Hirons and R.D. O'Dell,
CDC-6600 Version of 2DB, A Two-dimensional Diffusion-burnup Codefor Fast Reactor Analyses, LASL Note K-1-l-776, February 5, 1969.
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Scientific Laboratory (unpublished).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.
|Package ID||Computer language|
|File name||File description||Records|
|NESC0325_02.002||SUBROUTINES ETIME,NTRAN & DATA INPUT||130|
Keywords: criticality searches, depletion, diffusion equations, multigroup, r-theta, r-z, reactivity, two-dimensional, x-y.