Computer modelling of fuel behaviour and performance in research reactors as related to fuel depletion

The code ISODEP is being developed to compute the rate of production of nuclides in different homogeneous zones of a research reactor. ISODEP will form part of a main programme MEPE for analysis of the Miniature Neutron Source Reactor. An exponential method proposed by Hansen is the basis for the numerical solution of non-homogeneous simultaneous equations which describe the rate of production and decay of nuclides. Four principal chains associated with uranium-fuelled reactor were studied. The trend of results was found to be consistent with those obtained by analytical method. It is hoped that after slight modifications of the code and with appropriate effective microscopic cross-section data it will be suitable for research reactor analysis. (author)