CCC-0709 TDTORT.

1. NAME OR DESIGNATION OF PROGRAM:  TDTORT.

3. DESCRIPTION OF PROGRAM OR FUNCTION

TDTORT solves the time-dependent, three-dimensional neutron transport equation with explicit representation of delayed neutrons to estimate the fission yield from fissionable material transients. This release includes a modified version of TORT from the C00650MFMWS01 DOORS3.1 code package plus the time-dependent TDTORT code. GIP is also included for cross-section preparation.

TORT calculates the flux or fluence of particles due to particles incident upon the system from extraneous sources or generated internally as a result of interaction with the system in two- or three-dimensional geometric systems. The principle application is to the deep-penetration transport of neutrons and photons. Reactor eigenvalue problems can also be solved. Numerous printed edits of the results are available, and results can be transferred to output files for subsequent analysis.

TDTORT reads ANISN-format cross-section libraries, which are not included in the package. Users may choose from several available in RSICC's data library collection which can be identified by the keyword "ANISN FORMAT."

4. METHODS

The time-dependent spatial flux is expressed as a product of a space-, energy-, and angle-dependent shape function, which is usually slowly varying in time and a purely time-dependent amplitude function. The shape equation is solved for the shape using TORT; and the result is used to calculate the point kinetics parameters (e.g., reactivity) by using their inner product definitions, which are then used to solve the time-dependent amplitude and precursor equations. The amplitude function is calculated by solving the kinetics equations using the LSODE solver. When a new shape calculation is needed, the flux is calculated using the newly computed amplitude function.

The Boltzmann transport equation is solved using the method of discrete ordinates to treat the directional variable and weighted finite-difference methods, in addition to Linear Nodal and Linear Characteristic methods in TORT to treat spatial variables. Energy dependence is treated using a multigroup formulation. Starting in one corner of a mesh, at the highest energy, and with starting guesses for implicit sources, boundary conditions and recursion relationships are used to sweep into the mesh for each discrete direction independently. Integral quantities such as scalar flux are obtained from weighted sums of the directional results. The calculation then proceeds to lower energy groups, one at a time.

Iterations are used to resolve implicitness caused by scattering between directions within a single energy group, by scattering from an energy group to another group previously calculated, by fission, and by certain types of boundary conditions. Methods are available to accelerate convergence of both inner and outer iterations. Anisotropic scattering is represented by a Legendre expansion of arbitrary order, and methods are available to mitigate the effect of negative scattering source estimates resulting from finite truncation of the expansion. Direction sets can bebiased, concentrating work into directions of particular interest. Fixed sources can be specified at either external or internal mesh boundaries, or distributed within mesh cells.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

TORT's limitations for solving a three-dimensional, fixed source problem apply (i.e., geometry, convergence, non-linear effects, etc.). External forces and nonlinear physical effects cannot be treated. Penetration through large, non-scattering regions may become inaccurate due to ray effects. Problems with scattering ratios near unity or eigenvalue calculations with closely spaced eigenvalues may be quite time-consuming. Although flexible dimensioning is used in TORT so that no fixed limits on group, problem size, etc., are applicable, TDTORT uses a fixed size container array, which may not be big enough for very large problems. The user should change the value of isdim in comsd3.F and recompile. When the size is not sufficient, the code will indicate how much it needs (which can be used to determine the new size).

6. TYPICAL RUNNING TIME

Running time is roughly proportional to the number of fixed source (flux update) calculations each being proportional to mesh cells, directions, groups, and iterations. The codes compiled in only a few minutes. Test cases ran in about 47 minutes on a Sun UltraSparc 60, in 19 minutes on a DEC, and in 18 minutes on Pentium III 450Mhz computer.

8. RELATED OR AUXILIARY PROGRAMS:  GIP: Group cross-section preparation.

10. REFERENCES

S. Goluoglu, H.L. Dodds, "A Time-Dependent, Three-Dimensional Neutron Transport Methodology," Nucl. Sci. Eng., 139, 248-261 (2001).

- S. Goluoglu:
A Deterministic Method for Transient, Three-Dimensional Neutron Transport
Ph.D. Dissertation, Nuclear Engineering Department,
The University of Tennessee, Knoxville (August 1997).
- W. A. Rhoades and D. B. Simpson:
The TORT Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code
ORNL/TM-13221 (October 1997).
- W. A. Rhoades and M. B. Emmett:
the GIP section of "DOS: The Discrete Ordinates System,
ORNL/TM-8362 (September 1982).

11. HARDWARE REQUIREMENTS

TDTORT was developed on Sun workstations. It was compiled, and test cases were run on DEC Alpha Digital Unix workstations and personal computers under Linux.

13. SOFTWARE REQUIREMENTS

The codes run under Unix or Linux. Fortran and C compilers are required for installation on Unix systems. Executables created with the Portland Group Inc.Workstation 3.3 f77 compiler are included for Linux users. TDTORT was tested at RSICC on the following systems:

Sun SparcStation 60, OS5.6, SUN Fortran 77 Ver 5

DEC 500au, Digital UNIX 4.00, Digital Fortran 77 Version 5.6-075

Pentium III 450Mhz under RedHat Linux 6+ with PGI Workstation 3.3 f77

15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by:
                    Radiation Safety Information
                    Computational Center
                    Oak Ridge National Laboratory
                    Oak Ridge, Tennessee, U. S. A.

Developed by:
                    The University of Tennessee,
                    Nuclear Engineering Department,
                    Knoxville, Tennessee, U.S.A.

Readme.txt   Information file
TDTORT-manual.doc  Manual (Word file)
buildall  compile, load, run script
run_linux  script to run test cases on linux using distributed PGI executables
bin_linux  PGI executables for Linux
gip_dec  GIP source for DEC
gip_linux  GIP source for Linux
gip_sun  GIP source for Sun
tdtort_dec   TDTORT source for DEC
tdtort_sun  TDTORT source for Sun & Linux
testorg_dec  Dec result files for comparison
testorg_linux  Linux result files for comparison
testorg_sun  Sun result files for comparison
testsave  test case input
tort_dec  TORT source for DEC
tort_sun  TORT source for Sun & Linux
C709.PDF Documentation in electronic form