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RSIC CODE PACKAGE CCC-159




1. NAME AND TITLE

ORPHEE VI: Kernel Integration Code System Attenuation of Fast Neutrons in Cylindrical Layers of Water and Dense Material.

This code package represents early work of the French (CEA) Shielding Laboratory, now located at the CEA/CEN/Saclay. It is retained for reference.

2. CONTRIBUTOR

CEA/CEN Fontenay-aux-Roses Nuclear Research Center, France.

3. CODING LANGUAGE AND COMPUTER

FORTRAN IV and some Assembly Language; IBM 360.

4. NATURE OF PROBLEM SOLVED

The attenuation of fast neutrons is calculated by an empirical kernel. The geometry is a succession of heavy media separated by thin layers of water in a cylindrical geometry. The description of the source by bundles renders it particularly suited to light water power reactors. The fast neutron flux is given for each group of cores and for each height of rods.

5. METHOD OF SOLUTION

The coefficients of the empirical kernel, including a buildup factor and removal cross sections, are determined from either Monte Carlo or discrete ordinates calculations. The kernel is integrated over a power distribution given by the product of radial and vertical distributions S(x,y) f(z) where f(z) is a cosine function.

6. RESTRICTIONS OR LIMITATIONS

The limits on input parameters are documented.

7. TYPICAL RUNNING TIME

No study has been made by RSIC of typical running times for ORPHEE VI. The author indicates that ORPHEE VI considers the given radial distribution, element by element, and the actual axial distribution in about 1 minute per point on the IBM 360/50.

8. COMPUTER HARDWARE REQUIREMENTS

The code was designed for the IBM 360/50. The packaged version is operable on the IBM 360/50/75/91 computer configurations.

9. COMPUTER SOFTWARE REQUIREMENTS

The IBM 360 FORTRAN IV compilers may be used. A few routines are written in assembly language.

10. REFERENCE

M. Simon, "ORPHEE VI Program, Attenuation of Fast Neutrons in a Structure Consisting of Layers of Water and Dense Material," CEA-N-1244 (ORNL-tr-2357) (January 1970).

11. CONTENTS OF CODE PACKAGE

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

12. DATE OF ABSTRACT

June 1972; reviewed December 1984.

KEYWORDS: KERNEL; NEUTRON; ONE-DIMENSION