Book/Report

FZJ-2016-04887

http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png ACFA - a versatile activation code for coolant and structural materials

Brockmann, H.FZJ* ; Ohlig, U.FZJ*

1983
Kernforschungsanlage Jülich GmbH, Zentralbiliothek, Verlag Jülich

Please use a persistent id in citations: http://hdl.handle.net/2128/12356

Report No.: Juel-1866

Abstract: The ACFA code calculates the neutron-induced activation, afterheat, transmutation, gas production, biological hazard potential, and activation gamma ray spectra in the components of a nuclear system. The quantities of interest may be computed by spatial interval and zone or only 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 multigroup 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 code uses a variable dimensioning technique to adapt the core data storage requirements to the particular problem considered and uses the FIDO inputsystem to read the input data. The numerical methods for establishing and solving the decay chain equations are taken from theORIGEN code. To test the ACFA code and the nuclear data libraries used, the activation, composition change, and gas production inthe first wall of the UWMAK-I fusion reactor are calculated. The results of the activation calculation are compared with earlier results of the University of Wisconsin Fusion Study Group.

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Contributing Institute(s):

1. Publikationen vor 2000 (PRE-2000 ; Retrocat)

Research Program(s):

1. 899 - ohne Topic (POF3-899) (POF3-899)

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Database coverage:

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