1. NAME AND TITLE

TRANSX-CTR: Interfaces MATXS Cross-Section Libraries to Nuclear Transport Codes for Fusion Systems Analysis.

AUXILIARY CODES

BBC: Converts formatted MATXS libraries to binary mode.

CCC: Converts TRANSX-CTR source between long-word machines and short-word machines.

Several libraries in MATXS format are available from RSIC: DLC-114/MATXS1, DLC-115/MATXS5A, DLC-116/MATXS6A, and DLC-117/MATXS7A.

2. CONTRIBUTORS

Los Alamos National Laboratory, Los Alamos, New Mexico.

Knolls Atomic Power Laboratory, Schenectady, New York.

3. CODING LANGUAGE AND COMPUTER

Fortran 77; CDC 7600, Cray, IBM, VAX.

4. NATURE OF PROBLEM SOLVED

TRANSX-CTR is a computer code that reads nuclear data from a library in MATXS format and produces transport tables with many discrete-ordinates (Sn) and diffusion codes. Tables can be produced for neutron, photon, or coupled transport. Options include adjoint tables, mixtures, self-shielding, group collapse, homogenization, thermal upscatter, prompt or steady-state fission, transport corrections, elastic removal corrections, and flexible response-function edits. The ability to prepare coupled tables and response edits for heating, damage, gas production, and delayed activity makes TRANSX-CTR especially useful for fusion reactor studies.

5. METHOD OF SOLUTION

Discrete-ordinates (Sn) transport codes that solve the Boltzmann equation for the distribution of neutrons and photons in nuclear systems have reached a high level of development. The utility code called TRANSX-CTR (for transport cross-section code) works together with a generalized cross-section library called MATXS (for material cross sections) to give the transport code user easier access to appropriate nuclear data.

6. RESTRICTIONS OR LIMITATIONS

None noted.

7. TYPICAL RUNNING TIME

The sample problem that is packaged was run on the CDC 7600 computer using scope 2.1.

8. COMPUTER HARDWARE REQUIREMENTS

This version of TRANSX-CTR is operable on several computers.

9. COMPUTER SOFTWARE REQUIREMENTS

Fortran 77 on several systems.

10. REFERENCES

R. E. MacFarlane, Transmittal letter for TRANSX-CTR, LANL (March 6, 1984).

R. E. MacFarlane, "A Code for Interfacing MATXS Cross-Section Libraries to Nuclear Transport Codes for Fusion Systems Analysis," LA-9863-MS (February 1984).

A. Barnett, Modifications required for UNICOS installation, KAPL (February 16, 1989).

11. CONTENTS OF CODE PACKAGE

Included are the referenced documents and one (360KB) DOS diskette which contains the source code, sample problem input and output.

12. DATE OF ABSTRACT

May 1984; update October 1984, April 1985, November 1987, February 1989, and January 1991.