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[Program Service | Recent programs]

NEA-1072 ACFA. (Abstract last modified 21-DEC-1987)


ACFA, Isotope Activation of Coolant and Structure Materials

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Abstract Table of Contents:

NAME | COMPUTER | PROBLEM | SOLUTION | RESTRICTIONS | CPU | FEATURES | AUXILIARIES | STATUS | REFERENCES | REQUIREMENTS | LANGUAGE | OPERATING SYSTEM | OTHER RESTRICTIONS | AUTHOR | MATERIAL | CATEGORIES |

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1. NAME OR DESIGNATION OF PROGRAM - ACFA. 


2. COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE -

To request or retrieve programs click on the one of the active versions below. A password and special authorization is required.

Explanation of the status codes.

Program-name         Package-ID  Status
ACFA                 NEA-1072/01 Obsolete
ACFA                 NEA-1072/02 Tested

Machines used:
Package-ID     Orig.Computer                       Test Computer
NEA-1072/02    IBM 3033                            IBM 3084

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.


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.


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.


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.


7. UNUSUAL FEATURES OF THE PROGRAM - 


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). 


9. STATUS
NEA-1072/01: 20-APR-2000 Obsolete
NEA-1072/02: 21-DEC-1987 Tested at NEADB


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


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.


12. PROGRAMMING LANGUAGE(S) USED -
NEA-1072/02: FORTRAN+ASSEMBLER 


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.


14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS - 


15. NAME AND ESTABLISHMENT OF AUTHORS - 
Contributed by:   Kernforschungsanlage Juelich GmbH 
                  5170 Juelich, Federal Republic of Germany 


16. MATERIAL AVAILABLE -
NEA-1072/02:
ACFA Source Program                        
FIDO Subroutines                           
DATIM Subroutines (Assembler)              
JOBNUM Subroutines (Assembler)             
Job Control Cards                          
Decay Data Library                         
Photon Yield Library                       
UKCTRIIIA Activation Cross-Section Library 
Input Data for ACFA Sample Problem         
Output from ACFA Sample Problem            
REDUCE Source Program                      
report                   Juel-1866  (September 1983)                REPPT


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

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