1. NAME AND TITLE
TRANSX-CTR: Interfaces MATXS Cross-Section Libraries to Nuclear Transport Codes
for Fusion Systems Analysis.
BBC: Converts formatted MATXS libraries to binary mode.
CCC: Converts TRANSX-CTR source between long-word machines and short-word
Several libraries in MATXS format are available from RSIC: DLC-114/MATXS1, DLC-115/MATXS5A, DLC-116/MATXS6A, and DLC-117/MATXS7A.
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
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.
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.
KEYWORD: MULTIGROUP CROSS SECTION PROCESSING; SELF SHIELDING; MATXS FORMAT