1. NAME AND TITLE
NUFACE: An Interface Code For The Calculation Of Nuclear Responses.
AUXILIARY PROGRAMS
CRESPLIB: A Code To Convert the Response Function Library To Binary Form.
CCC-547/TWODANT-SYS: A One and Two-Dimensional Multigroup Discrete Ordinates
Transport Code System.
2. CONTRIBUTOR
Oak Ridge National Laboratory, Oak Ridge, Tennessee.
3. CODING LANGUAGE AND COMPUTER
Fortran 77; Cray computers.
4. NATURE OF PROBLEM SOLVED
NUFACE calculates nuclear responses, such as first wall and toroidal field coil irradiation damage
limits, the tritium breeding ratio, the helium and hydrogen production rates, and the fast neutron
fluence for a given tokamak fusion reactor.
5. METHOD OF SOLUTION
NUFACE computes nuclear response rates using the scalar and angular neutron fluxes computed
by the ONEDANT code (CCC-547) and the MACKLIB-IV response functions. The response function
library is converted to binary form by CRESPLIB. The calculation of the zone-integrated response
rates is performed by multiplying the neutron (gamma) flux at a given position, by the response
function of interest and summing over all constituents and fine-mesh cells within the zone. Zone-boundary responses are calculated by multiplying the zone-boundary flux by the response functions.
6. RESTRICTIONS OR LIMITATIONS
NUFACE uses the fluxes as computed by ONEDANT (CCC-547). The MACKLIB-IV response
function data is in a 46 neutron, 21 gamma group structure.
7. TYPICAL RUNNING TIME
On a Cray XMP/14, the ONEDANT run to create the input fluxes to NUFACE took about 52
seconds. The creation of a binary library with the code CRESPLIB took about 3 seconds. NUFACE
took about 1 second of CPU time on the sample problem.
8. COMPUTER HARDWARE REQUIREMENTS
NUFACE runs on the Cray XMP.
9. COMPUTER SOFTWARE REQUIREMENTS
The code was written in Fortran 77. It runs under both CTSS and UNICOS operating systems.
Under UNICOS, the CFT77 compiler is used.
10. REFERENCES
D. L. Henderson and I. C. Gomes, "NUFACE: An Interface Code For The Calculation Of Nuclear Responses," ORNL/FEDC-90/2 (January 1990).
XSLIB summary, informal notes (1990).
11. CONTENTS OF CODE PACKAGE
Included are the referenced document and two (1.2MB) DOS diskettes.
12. DATE OF ABSTRACT
January 1991.
KEYWORDS: KERMA; NEUTRON; OPTIMIZATION; RADIATION DAMAGE