1. NAME AND TITLE

SUSD: Cross Section Sensitivity and Uncertainty Analysis Including Secondary Neutron Energy and Angular Distributions.

2. CONTRIBUTORS

University of Tokyo, Tokyo, Japan.

NEA Data Bank, Gif-sur-Yvette Cedex, France.

3. CODING LANGUAGE AND COMPUTER

Fortran 77; HITACHI-M Series (A), IBM 3090 and VAX 8810 (B).

4. NATURE OF PROBLEM SOLVED

SUSD calculates sensitivity coefficients for one- and two-dimensional transport problems. Variance and standard deviation of detector responses or design parameters can be obtained using cross-section covariance matrices. In neutron transport problems, this code can perform sensitivity-uncertainty analysis for secondary angular distribution (SAD) or secondary energy distribution (SED).

5. METHOD OF SOLUTION

SUSD uses first order perturbation theory to calculate sensitivity coefficients. The system includes additional modules for the PSR-171/NJOY system to prepare partial cross sections for SAD sensitivity analysis (GROUPSR) and group covariance matrices for SAD/SED uncertainty analysis (SEADR).

6. RESTRICTIONS OR LIMITATIONS

None noted.

7. TYPICAL RUNNING TIME

Each code ran in less than a second at NEADB on the IBM 3090.

8. COMPUTER HARDWARE REQUIREMENTS

SUSD is operable on the HITACHI M-150 H computer, IBM 3090 and VAX 8810.

9. COMPUTER SOFTWARE REQUIREMENTS

A Fortran 77 compiler is necessary to compile the source. On the IBM 3090, VS Fortran 2.1.1 was used under the MVS/XA operating system. On the VAX 8810, VAX Fortran 5.0-1 was used under the VMS operating system.

10. REFERENCE

K. Furuta, Y. Oka, S. Kondo, "SUSD: A Computer Code for Cross-Section Sensitivity and Uncertainty Analysis Including Secondary Neutron Energy and Angular Distributions," ORNL/TR-88/18 (November 1988).

11. CONTENTS OF CODE PACKAGE

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

12. DATE OF ABSTRACT

December 1988; March 1991.