1. NAME AND TITLE
PN: MultiGroup Neutron Transport.
2. CONTRIBUTOR
Central
Technical Services, Risley, United Kingdom through the OECD Nuclear Energy
Agency Data Bank, Issy-les-Moulineaux, France.
3. CODING LANGUAGE AND COMPUTER
Fortran IV; IBM 370 Series (C00818I037000).
4. NATURE OF PROBLEM SOLVED
PN solves the static multigroup neutron transport equation in one, two or three dimensions.
5. METHOD OF SOLUTION
The flux is expanded in spherical harmonics. Diffusion type equations are obtained for the even moments and these are solved using over relaxation methods.
6. RESTRICTIONS OR LIMITATIONS
10000 mesh points in 37 groups.
7. TYPICAL RUNNING TIME
Problem dependent.
8. COMPUTER HARDWARE REQUIREMENTS
IBM 370 Series - 590 kbytes of fast store and 6 disc files.
9. COMPUTER SOFTWARE REQUIREMENTS
RIOS of ICL 470. OS of IBM 370.
10. REFERENCES
a) Included Documentation
J. K. Fletcher, “The Solution of the Multigroup Neutron Transport Equation Using Spherical Harmonics,” The Reactor Group, United Kingdom Atomic Energy Authority, TRG Report 2547(R) (August 1974).
11. CONTENTS OF CODE PACKAGE
The package is distributed on a CD with a compressed zip file including source files, JCL, documentation and sample data and output.
12. DATE OF ABSTRACT
December 2013.
KEYWORDS: MULTIGROUP, NEUTRON TRANSPORT THEORY, ONE-DIMENSIONAL, SPERICAL HARMONICS, THREE-DIMENSIONAL, TWO-DIMENSIONAL