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NEA-1072 ACFA.

ACFA, Isotope Activation of Coolant and Structure Materials

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1. NAME OR DESIGNATION OF PROGRAM:  ACFA.
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2. COMPUTERS
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Program name Package id Status Status date
ACFA NEA-1072/02 Tested 21-DEC-1987

Machines used:

Package ID Orig. computer Test computer
NEA-1072/02 IBM 3033 IBM 3084
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3. DESCRIPTION OF PROGRAM OR FUNCTION

The ACFA code calculates the neutron-induced activation, afterheat, biological hazard potential,  transmutation and gamma-ray spectra in a nuclear system. The quantities of interest may be calculated by interval and/or by zone  of the system considered. To calculate the transmutation coefficients for the neutron - induced reactions the code uses multigroup activation cross sections and space - dependent multi- group neutron fluxes in one- or two-dimensional geometry. The neutron reaction types incorporated in the code are (n,n'), (n,2n),  (n,gamma), (n,p), (n,alpha), (n,n'p), (n,n'alpha), (n,t), (n,3n), (n,He-3), (n,d), and (n,n'd) considering both reactions to the ground state and to isomeric states.
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4. METHOD OF SOLUTION

The code uses the matrix exponential method and the Bateman solution to solve a large system of coupled linear first-order ordinary differential equations with constant coefficients.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The code is flexibly dimensioned which means that the storage requirements are determined for the particular problem at execution time. The length of the decay chains constructed by the code only depends on the decay and cross section data given in the nuclear data libraries.
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6. TYPICAL RUNNING TIME

It is difficult to assign a typical running time since it depends on the number of nuclides, number of space points and number of irradiation and postirradiation times.  The packaged sample problem uses 784 nuclides, 4 space points, 3 irradiation times and 9 postirradiation times. The running time for  the GO step is 1 min 54 sec on the IBM-3081.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

The numerical methods for solving the equations are taken from the ORIGEN code.
DATA LIBRARIES:
     Decay data library (784 nuclides).
     100 Group activation cross section library (1,477 reactions).
     Photon yield library (1209 nuclides).
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9. STATUS
Package ID Status date Status
NEA-1072/02 21-DEC-1987 Tested at NEADB
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10. REFERENCES

- H.J. Bell,
  "ORIGEN - The ORNL Isotope Generation and Depletion Code",
  ORNL - 4628, Oak Ridge National Laboratory (1973).
NEA-1072/02, included references:
- H. Brockmann and U. Ohlig:
  ACFA - A Versatile Activation Code for Coolant
  and Structural Materials.
  Juel-1866  (September 1983)
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11. MACHINE REQUIREMENTS

The ACFA code was designed to run on the IBM  3033 and 3081 machines. The various calculational options require from four to eight direct access devices, depending on the problem.  Furthermore, the standard input-output units are used.
NEA 1072/01: The test case included in this package ran on an IBM3084 computer in 740K bytes of main storage.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1072/02 FORTRAN+ASSEMBLER
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

ACFA is operable  on the IBM OS 360 with FORTRAN H Extended Compiler. The program consists of 34 subroutines on 3,707 source cards. Standard software  may be used for the ACFA code. Any non-standard library routines which are used have been included in the code package. The required  decay data library, activation cross section library, and photon yield library are also included in the code package.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by:   Kernforschungsanlage Juelich GmbH
                  5170 Juelich, Federal Republic of Germany
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16. MATERIAL AVAILABLE
NEA-1072/02
source program   mag tapeACFA Source Program                        SRCTP
source program   mag tapeFIDO Subroutines                           SRCTP
source program   mag tapeDATIM Subroutines (Assembler)              SRCTP
source program   mag tapeJOBNUM Subroutines (Assembler)             SRCTP
test-case data   mag tapeJob Control Cards                          DATTP
test-case data   mag tapeDecay Data Library                         DATTP
test-case data   mag tapePhoton Yield Library                       DATTP
test-case data   mag tapeUKCTRIIIA Activation Cross-Section Library DATTP
test-case data   mag tapeInput Data for ACFA Sample Problem         DATTP
test-case output mag tapeOutput from ACFA Sample Problem            OUTTP
source program   mag tapeREDUCE Source Program                      SRCTP
report                   Juel-1866  (September 1983)                REPPT
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: activation, biological hazard potential, coolants, decay spectra, neutron cross sections, radiation heat, structural beams, transmutation.