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RSIC CODE PACKAGE CCC-490






1. NAME AND TITLE

PRIMEDANA-2: Collapses Multigroup Cross Sections and Obtains Reaction Parameters by Solving Transport or Diffusion Equations.

AUXILIARY ROUTINES

TEMPO: Produces effective cross sections for COLAPS, MED or ANALITS.

COLAPS: Collapses multigroup cross sections.

MEDS: Multigroup one-dimensional code for neutron physics computation of multizone fast breeders.

ANALITS: Source iteration method of solving multigroup diffusion equation.

DATA LIBRARIES

BNAB-78: 26 neutron group cross section library.

BNAB-64: 26 neutron group cross section library.

2. CONTRIBUTOR

Institute for Nuclear Research and Nuclear Energy, Bulgarian Academy of Sciences, Sofia, Bulgaria.

3. CODING LANGUAGE AND COMPUTER

Fortran IV; EC 1040 and IBM 3081.

4. NATURE OF PROBLEM SOLVED

PRIMEDANA-2 is a modular code system for neutron physics calculations of fast reactors.

5. METHOD OF SOLUTION

PRIMEDANA-2 prepares effective multigroup microscopic and macroscopic cross sections for compositions characteristic of fast neutron reactors. The shielding factor approach is used. Optionally the multigroup cross section library can be collapsed to a few-group cross section library. The multigroup diffusion equation is solved using the method of the central finite differences and/or a new semi-analytical method.

6. RESTRICTIONS OR LIMITATIONS

None noted.

7. TYPICAL RUNNING TIME

Sample cases execute in less than one minute on the IBM.

8. COMPUTER HARDWARE REQUIREMENTS

PRIMEDANA-2 was developed on the EC 1040 and runs on the IBM 360/370 and IBM 3081 computers.

9. COMPUTER SOFTWARE REQUIREMENTS

A Fortran IV compiler is required.

10. REFERENCE

J. D. Jordanov and P. P. Groudev, "User's Guide for PRIMEDANA-2 System," Institute for Nuclear Research and Nuclear Energy, Bulgaria (1988).

11. CONTENTS OF CODE PACKAGE

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

12. DATE OF ABSTRACT

July 1986; revised October 1987, April 1989 and November 1989.

KEYWORDS: NEUTRON; CROSS SECTION PROCESSING