1. NAME AND TITLE

FISPIN: Nuclide Inventory Calculation System.

2. CONTRIBUTOR

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 approximate method.

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 time.

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.

10. REFERENCE

R. F. Burstall, "FISPIN A Computer Code for Nuclide Inventory Calculations," ND-R-328(R) (October 1979).

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.