1. NAME AND TITLE
SAIPS: Information Processing System for Calculating Neutron Spectra from Measured
Latvian University, Riga, Latvia.
3. CODING LANGUAGE AND COMPUTER
Fortran 77; IBM PC and compatibles.
4. NATURE OF PROBLEM SOLVED
The SAIPS information and computing system solves the problem of program organization and
processing of data sets used for unfolding neutron spectra.
5. METHOD OF SOLUTION
The SAND-II, WINDOWS, RFSP-JUL programs have been incorporated into SAIPS. SAND-II is an iterative method for neutron flux spectra determination by multiple foil activation. WINDOWS analyzes spectra data foil activation measurements using integral responses, i.e., integrals of weighting functions against the neutron flux. RFSP-JUL calculates the spectral neutron flux density from activity measurements, guess spectrum, and cross section data.
Several cross-section libraries have been adapted for SAIPS including ENDF/B-IV, ENDF/B-V, the
dosimetric file ZACRSS, and BOSPOR 78. SAIPS contains cross-sections for more than 80 reactions
used in unfolding. In performing calculations, it is possible to use several spectra libraries as a source
of first approximation.
6. RESTRICTIONS OR LIMITATIONS
|Number of Energy
Groups or Points
Up to 100
7. TYPICAL RUNNING TIME
The code is interactive and run times are dependent on the calculation performed.
8. COMPUTER HARDWARE REQUIREMENTS
SAIPS is operable on an IBM PC with a math co-processor.
9. COMPUTER SOFTWARE REQUIREMENTS
A Fortran 77 compiler is required. The test compiler was RM/Fortran Version 2.42.
a. Included in the documentation:
M. Berzonis. "AIPS (PC Version) - User's Manual 1989," informal document (March 1990).
b. Background information:
M. A. Berzonis, H. Ya. Bondars, "Methods of Neutron Spectrum Calculation from Measured
Reaction Rates in SAIPS. Part 2: Software and Data Input," INDC(CCP)-165/GR (August 1981).
11. CONTENTS OF CODE PACKAGE
Included are the referenced document and 2 DS/HD 5.25-inch diskettes (1.2 MB) which contains
the source codes, cross section libraries, input spectra, and sample problem input.
12. DATE OF ABSTRACT
KEYWORDS: MICROCOMPUTER; INTERACTIVE, ON-LINE; ACTIVATION DETECTORS; ENDF/B-V; NEUTRON CROSS SECTION PROCESSING