NEA-1072 ACFA.
ACFA, Isotope Activation of Coolant and Structure Materials
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES
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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.
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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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.
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.
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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10. REFERENCES
- H.J. Bell,
"ORIGEN - The ORNL Isotope Generation and Depletion Code",
ORNL - 4628, Oak Ridge National Laboratory (1973).
- 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.
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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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.
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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NEA-1072/02
source program mag tapeACFA Source Program SRCTPsource 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
Keywords: activation, biological hazard potential, coolants, decay spectra, neutron cross sections, radiation heat, structural beams, transmutation.