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RSIC CODE PACKAGE PSR-115


1. NAME AND TITLE

SUPERTOG-JR.: A Code System for Generating Transport Group Constants, Energy Deposition Coefficients and Atomic Displacement Constants with ENDF/B.

The multigroup cross section production code system SUPERTOG is widely used as a standard process code for use in the Sn-type transport code. Capabilities were added in SUPERTOG-JR. which increase the utility of the code.

2. CONTRIBUTOR

Japan Atomic Energy Research Institute, Tokai, Ibaraki, Japan, and OECD NEA Data Bank, Gif-sur-Yvette, France.

3. CODING LANGUAGE AND COMPUTER

Fortran IV; FACOM 230-75 (A), IBM 360/370 (B).

4. NATURE OF PROBLEM SOLVED

SUPERTOG-JR. generates (a) the neutron cross sections for neutron transport calculation and (b) the energy deposition coefficients and the atomic displacement cross sections from the basic data given in ENDF/B.

5. METHOD OF SOLUTION

Function (a) is the same as in PSR-13/SUPERTOG-3 except that elastic scattering transfer matrices can be calculated from either tabular or Legendre representation. In addition, an optional routine generating the inelastic scattering matrix in the level density model is provided. Function (b) treats both in nearly the same mathematical formulae except for the conversion scheme of kinetic energy of neutrons onto the material atoms. The displacement cross section is calculated with the Lindhard model.

6. RESTRICTIONS OR LIMITATIONS

None noted.

7. TYPICAL RUNNING TIME

No study has been made by RSIC of typical running times for SUPERTOG-JR.

8. COMPUTER HARDWARE REQUIREMENTS

SUPERTOG-JR. is operable on the FACOM 230-75 (A) or the IBM 360/370 computers.

9. COMPUTER SOFTWARE REQUIREMENTS

A Fortran IV compiler is required.

10. REFERENCE

Y. Taji, T. Okada, K. Minami and S. Miyasaka, "SUPERTOG-JR, A Code Generating Transport Group Constants, Energy Deposition Coefficients and Atomic Displacement Constants with ENDF/B," JAERI-M 6935 (January 1977).

11. CONTENTS OF CODE PACKAGE

Included are the referenced document and one (1.2MB) DOS diskette which contains the source code, library data, and sample problem input and output.

12. DATE OF ABSTRACT

March 1984, updated December 1991.

KEYWORDS: MULTIGROUP CROSS SECTION PROCESSING; NEUTRON CROSS SECTION PROCESSING