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NESC0558 TASK

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

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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. REFERENCE

- 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.