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RSIC CODE PACKAGE PSR-284


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