Changes in haematological levels in gamma irradiated Nile-catfish clarias lazera

The aim of this work is to find a method for calculating the slowing down parameters and the data to be used for several types of reactors. The treatment is based on a multigroup collision probability model. In this work 64 groups are used for the slowing down region till the cut-off energy, and one thermal group is used to get the multiplication factor. A good test of this method, as well as of the nuclear data used, is the comparison of age calculated by this method and experimental results. It is tested for light water and graphite reactors. The second part of this work is concerned with flux calculations in light water and graphite reactors, using the slowing down method mentioned above. Ten cases, with different composition, are used for water cells. The enrichment of fuel varies from 1.04% to 1.3%. The moderator to fuel volume ratio varies from 1 to 4. Also another 9 different graphite natural uranium cells, with different moderator to fuel volume ratio, between 34 and 76, are considered. Heterogeneous cells are treated as homogeneous ones, to test the effect of homogeneization on heterogeneous reactor cells (since calculations for homogeneized cells are easier and take negligible time in computation). (author)