1. NAME AND TITLE
FISPIN: Nuclide Inventory Calculation System.
UKAEA/Risley Nuclear Power Development Establishment, Warrington, England.
3. CODING LANGUAGE AND COMPUTER
Fortran IV; ICL 2982.
4. NATURE OF PROBLEM SOLVED
FISPIN calculates the production and removal of three groups of nuclides: the fission product
group, the actinide group, and the structural material group.
5. METHOD OF SOLUTION
The modes of production and removal of a nuclide are those of decay and of neutron reaction (of any type, including fission). The energies and intensities of the decaying nuclides are calculated for the various modes of decay, i.e., alpha, beta, gamma rays and spontaneous fission.
Since large numbers of nuclides may be involved, it is necessary to restrict the calculations in
certain ways, mainly by using an external flux spectrum and by calculating some nuclides by an
6. RESTRICTIONS OR LIMITATIONS
FISPIN does not include any means of calculating the neutron spectrum which must, therefore, be
input if multigroup cross-section libraries are used. The burnup calculations are performed in one
group only and multigroup cross sections are combined with an input spectrum, which may vary with
7. TYPICAL RUNNING TIME
No study has been made by RSIC of typical running times for FISPIN.
8. COMPUTER HARDWARE REQUIREMENTS
FISPIN is operable on the ICL 2982 computer.
9. COMPUTER SOFTWARE REQUIREMENTS
A Fortran IV compiler is required.
R. F. Burstall, "FISPIN A Computer Code for Nuclide Inventory Calculations," ND-R-328(R)
11. CONTENTS OF CODE PACKAGE
Included are the referenced document and one (1.2MB) DOS diskette which contains the source
code plus sample problem input and output.
12. DATE OF ABSTRACT
February 1982; revised February 1983.
KEYWORDS: ACTINIDES; ENDF/B FORMAT; ISOTOPE INVENTORY; FISSION PRODUCTS; ACTIVATION