A neutronic analysis of the first core of Iran 1+2 reactors

The objective of this analysis is to study some in-core parameters of the first core of Iran 1 and 2 reactors. For the calculations the burnup code BURNY-SQUID has been used. The computational schemes used have been discussed in section 1. A brief description of the code BURNY-SQUID is presented in section 2. Results of the criticality and burnup studies which include effect of spatial mesh size on the reactivity and flux shape, critical boron concentration, assembly wise power and burnup distributions, radial and axial power peaking factors, heavy isotope production and depletion, etc. have been given in section 3. Calculated values of the reactivity coefficients which include moderator and fuel temperature coefficients, power coefficients, boron coefficients and inverse boron worth, etc. are given in section 4. Whereever possible the calculated values have been compared with those supplied by the vendor KWU. A future plan of work is given in section 5. (Author)