Computer Programs

NESC0558 TASK

NESC0558 TASK

TASK, 1-D MultiGroup Diffusion or Transport Theory Reactor Kinetics with Delayed Neutron

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROBLEM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES

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1. NAME OR DESIGNATION OF PROGRAM: TASK

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2. COMPUTERS

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Program name	Package id	Status	Status date
TASK	NESC0558/01	Tested	01-SEP-1978

Machines used:

Package ID	Orig. computer	Test computer
NESC0558/01	IBM 370 series	IBM 370 series

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3. DESCRIPTION OF PROBLEM OR FUNCTION

TASK solves the one-dimensional multigroup form of the reactor kinetics equations, using either transport or diffusion theory and allowing an arbitrary number of delayed neutron groups. The program can also be used to solve standard static problems efficiently such as eigenvalue problems, distributed source problems, and boundary source problems. Convergence problems associated with sources in highly multiplicative media are circumvented, and such problems are readily calculable.

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4. METHOD OF SOLUTION

TASK employs a combination scattering and transfer matrix method to eliminate certain difficulties that arise in classical finite difference approximations. As such, within-group (inner) iterations are eliminated and solution convergence is independent of spatial mesh size. The time variable is removed by Laplace transformation. (A later version will permit direct time solutions.) The code can be run either in an outer iteration mode or in closed (noniterative) form. The running mode is dictated by the number of groups times the number of angles, consistent with available storage.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The principal restrictions are available storage and computation time. Since the code is flexibly-dimensioned and has an outer iteration option there are no internal restrictions on group structure, quadrature, and number of ordinates. The flexible-dimensioning scheme allows optional use of core storage. The generalized cylindrical geometry option is not complete in Version I of the code. The feedback options and omega-mode search options are not included in Version I.

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6. TYPICAL RUNNING TIME

A typical 13-region, 5-group, S4, fast reactor static problem requires about 0.5 minutes on the IBM360/91, whereas the entire kinetic response can be computed in 8 to 10 minutes. A 16-group, S16, static, 125-cm Fe slab shielding problem requires about 4 minutes.

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8. RELATED AND AUXILIARY PROGRAMS

Two auxiliary programs are included with TASK. Program ACPSD reads the flux tape(s) written (optionally) by TASK and computes an arbitrary number of detector responses, using detector energy responses as provided by the user and the group fluxes at space points selected by the user. The program also calculates the cross-power spectral density (CPSD) and auto-power spectral density (APSD) for selected pairs of detectors. Program FITSPEC fits the point reactor model to the real part of the cross-power spectral densities and to the auto-power spectral densities generated by program ACPSD.

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9. STATUS

Package ID	Status date	Status
NESC0558/01	01-SEP-1978	Tested at NEADB

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10. REFERENCES

REFERENCES
- A. R. Buhl, R. A. Lillie, H. L. Dodds, Jr., O. W. Hermann, J. C. Robinson, and R. J. Hinton:
A Users Manual for TASK, A Generalized One-dimensional Transport and Diffusion Kinetics Code, ORNL-TM-3811, December 1972.

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11. MACHINE REQUIREMENTS

TASK requires 154K bytes of storage plus data block storage and 1 tape if using the flux tape option.

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12. PROGRAMMING LANGUAGE(S) USED

Package ID	Computer language
NESC0558/01	FORTRAN+ASSEMBLER

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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED: OS/360.

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15. NAME AND ESTABLISHMENT OF AUTHORS

                 A. R. Buhl
                 Neutron Physics Division
                 O. W. Hermann and R. J. Hinton
                 Mathematics Division
                 Oak Ridge National Laboratory
                 Oak Ridge, Tennessee  37830
                 H. L. Dodds, Jr.
                 Savannah River Laboratory
                 E. I. duPont de Nemours and Company, Inc.
                 Aiken, South Carolina  29801
                 J. C. Robinson and R. A. Lillie
                 The University of Tennessee
                 Knoxville, Tennessee  37901

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16. MATERIAL AVAILABLE

NESC0558/01

File name	File description	Records
NESC0558_01.001	TASK - SOURCE PROGRAM (F4,EBCDIC)	3349
NESC0558_01.002	TASK - SUBROUTINES MODIFIED AT DATA-BANK	19
NESC0558_01.003	TASK - DD CARDS	4
NESC0558_01.004	TASK - SAMPLE PROBLEM INPUT DATA	1003
NESC0558_01.005	ACPSD - SOURCE PROGRAM (F4,EBCDIC)	349
NESC0558_01.006	ACPSD - SUBROUTINES MODIFIED AT DATA-BANK	16
NESC0558_01.007	ACPSD - DD CARDS	4
NESC0558_01.008	ACPSD - SAMPLE PROBLEM INPUT DATA	6
NESC0558_01.009	FITSPEC - SOURCE PROGRAM (F4,EBCDIC)	269
NESC0558_01.010	FITSPEC - SAMPLE PROBLEM INPUT DATA	261
NESC0558_01.011	ORNL SYSTEMS SUBROUTINE	908
NESC0558_01.012	ACPSD - PUNCHED CARD OUTPUT	20
NESC0558_01.013	TASK - SAMPLE PROBLEM PRINTED OUTPUT	9159
NESC0558_01.014	ACPSD - SAMPLE PROBLEM PRINTED OUTPUT	317
NESC0558_01.015	FITSPEC - SAMPLE PROBLEM PRINTED OUTPUT	714

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17. CATEGORIES

C. Static Design Studies
F. Space - Time Kinetics, Coupled Neutronics - Hydrodynamics - Thermodynamics

Keywords: multigroup, one-dimensional, reactor kinetics.