1. NAME AND TITLE
SUSD: Cross Section Sensitivity and Uncertainty Analysis Including Secondary Neutron
Energy and Angular Distributions.
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
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.
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.
KEYWORDS: ADJOINT, DISCRETE ORDINATES; MULTIGROUP; NEUTRON; SENSITIVITY ANALYSIS; PERTURBATION THEORY