1. NAME AND TITLE
SUPERTOG-JR.: A Code System for Generating Transport Group Constants, Energy
Deposition Coefficients and Atomic Displacement Constants with
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.
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
6. RESTRICTIONS OR LIMITATIONS
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.
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